progress report 2001 - 2002 - Intranet

INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES
RESEARCH REACTOR CENTER - CRPq
PROGRESS REPORT
2001 - 2002
Editor:
Artur Wilson Carbonari
Nuclear Physics Division
Research Reactor Center - CRPq
IPEN-CNEN/SP
Cx.Postal 11049, Pinheiros
05422-970 - São Paulo, SP
Tel.: (11)3816-9290
Fax.: (11)3816-9188
e-mail: [email protected]
Contents
Foreword
6
Neutron Activation and Radiochemical Analysis
Application of neutron activation analysis to studies of geological materials . . . . . . . . . . . . . . .
Determination of heavy metals in sediments for environmental contamination studies. . . . . . . . . .
Determination of platinum group elements and gold in reference materials by instrumental neutron
activation analysis and inductively coupled plasma-mass spectrometry with nickel sulphide fireassay collection. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Determination of trace elements elements in Tillandsia usneoides by neutron activation analysis for
environmental biomonitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Characterization of Brazilian prehistoric ceramics . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Evaluation of Mercury, MethylMercury and other elements of interest in fish, hair and diets of preschool children from Amazonic region. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Neutron activation analysis applied to the determination of chemical composition of metallic materials
Biomonitoring of toxic metals in marine organisms in the Coast of São Paulo by neutron activation
analysis and atomic absorption spectroscopy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Biomonitoring of air pollution through trace element analysis in Canoparmelia texana and Tradescantia
plant species . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Determination in vitro of inorganic components in human bone tissues by neutron activation analysis
Inorganic constituents and polymers determinations in metalized plastic materials from household waste
Contribution of the neutron activation analysis to evaluate the mineral absorption by Brachiaria Decumbens in function of the limestone doses used to recover and maintain heavily nitrogen-fertilized
tropical pastures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Application of neutron activation analysis to determine the essential and toxic elemental concentration
in grass forages cultivated on different soil types and management . . . . . . . . . . . . . . . . .
Determination of mineral and trace elements in brazilian foodstuffs by using neutron activation analysis.
7
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Nuclear Structure, Reactions and Metrology
The cadmium ratio technique for studying biological functions of mammalians submitted to uranium
ingestion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Cosmic ray chronometer 102m Rh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Effects of gamma radiation on the pbs-ks DNA plasmid . . . . . . . . . . . . . . . . . . . . . . . . .
Neutron flux distribution in an Am-Be neutron irradiator . . . . . . . . . . . . . . . . . . . . . . . .
Gamma-gamma angular correlation experiments performed with a multi-detector system . . . . . . .
Gamma spectroscopic study of excited levels in 193 Ir . . . . . . . . . . . . . . . . . . . . . . . . . . .
Nuclear structure of the low-lying states in the 72 Ge . . . . . . . . . . . . . . . . . . . . . . . . . . .
Measurements of photoneutron cross-sections for 9 Be, 13 C e 17 O nuclei using thermal neutron capture
gamma rays . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Electronic equilibrium study in aluminum using CaSO4 :Dy thermo luminescence dosimeter . . . . .
Standardization of 18 F radioactive solution using a 4πβ − γ coincidence system . . . . . . . . . . . .
Standardization of 186 Re radioactive solution . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Coincidence system for standardization of radionuclides using a 4π plastic scintillator detector . . .
Combination of nonlinear function and mixing method for fitting HPGe efficiency curve in the 59-2754
keV energy range . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
International comparison of 204 Tl radioactive solution . . . . . . . . . . . . . . . . . . . . . . . . . .
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Neutron Diffraction
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A new neutron powder diffractometer at the Research Reactor Center, IPEN . . . . . . . . . . . . . . 47
The hexagonal cell parameters of ß-quartz at 1003 k determined by neutron multiple diffraction . . . 49
Hyperfine Interactions
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Study of magnetic hiperfine fields acting on 140 Ce probes in some rare earth compounds by first
principles electronic structure calculations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 52
Temperature dependence of electric field gradient in LaCoO3 perovskite using perturbed angular correlation technique . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 54
3
Applied Physics and Instrumentation
Monte Carlo simulations of x-ray generation and detection . . . . . . . . . . . . . . . . . . . . . . . .
Small Furnace for Perturbed Angular Correlation Spectrometer . . . . . . . . . . . . . . . . . . . . .
A Routing Interface for the Multidetector Angular Correlation Spectrometer . . . . . . . . . . . . .
Electronic Control Module for a neutron Beam Shutter . . . . . . . . . . . . . . . . . . . . . . . . . .
Automatic Control System for Measuring Currents Produced by Ionization Chambers . . . . . . . .
Development of a dry fission track registration method to be employed in the uranium determination
for several biological and environmental samples . . . . . . . . . . . . . . . . . . . . . . . . . .
Neutron Radiography at CRPq . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Reactor Operation
IEA-R1 Research Reactor Operation and Maintenance . . . . . . . . . . . . . . . . . . . . . . . . . .
A remote radiation level monitoring system for the IEA-R1 reactor building in the case of a radiological
emergency . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Vibration Monitoring of the Primary Cooling Circuit Pumps of IEA-R1 Research Reactor . . . . . .
Corrective maintainance of the primary cooling circuit pumps of the IEA-R1 research reactor . . . .
Software for the preventive maintenance program of IEA-R1 reactor equipment . . . . . . . . . . . .
Neutronic and thermohydraulic calculations of the reactor IEA-R1 . . . . . . . . . . . . . . . . . . .
Area monitoring and radiation dose in the IEA-R1 reactor building . . . . . . . . . . . . . . . . . . .
Implementation of a quality management system at the Research Reactor Center . . . . . . . . . . .
Calibration of a Self Powered Neutron Detector SPND/Rhodium in the IEA-R1 Research Reactor by
Means of Activation Foils . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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Publications
Publications . . . . . . . . . . . . . . . . . . . . .
Papers published in Journals . . . . . . . .
Papers accepted for publication in Journals
Papers submitted for publication . . . . . .
Conference Proceedings . . . . . . . . . . .
Reports . . . . . . . . . . . . . . . . . . . .
Conference Contributions . . . . . . . . . . . . .
International Conferences . . . . . . . . . .
National Conferences . . . . . . . . . . . . .
Workshops . . . . . . . . . . . . . . . . . .
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Academic Activities
Dissertations and Theses . . . . . . . . . .
M.Sc. . . . . . . . . . . . . . . . . .
Ph.D. Thesis . . . . . . . . . . . . .
Courses offered . . . . . . . . . . . . . . .
Scientific Visits . . . . . . . . . . . . . . .
Pos-doctoral fellows and visiting scientists
Seminars . . . . . . . . . . . . . . . . . .
Research Grants . . . . . . . . . . . . . .
Scientific collaborations . . . . . . . . . .
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Services
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Personnel
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4
FOREWORD
The Research Reactor Center (CRPq) was formally created in the year 2000, integrating the former departments of Nuclear Physics and Chemistry
and Operation and Maintenance of Research Reactor
IEA-R1. Later in the same year the Nuclear Metrology Laboratory also joined the Center. CRPq was the
first among 10 R&D Centers, created under a technical and administrative reorganization of IPEN. The
reorganization contemplated increased administrative
and financial autonomy for the Centers in the management of their businesses. The General Manager of
the Center reports to the Technical and Administrative Council, consisting of board of directors and the
superintendent of the Institute.
The formation of CRPq was motivated by the long
perceived necessity of integrating all the activities involving operation and utilization of the research reactor IEA-R1, in a single compact administrative unit
which will also be responsible for the services and applications resulting from reactor utilization. In consonance with the Institute’s Director Plan, the Research
Reactor Center has a three-fold mission of promoting basic and applied research in nuclear and neutron related sciences, providing educational opportunities for students in these fields including Postgraduate and under-graduate teaching, and providing services and applications resulting from the reactor utilization. Four divisions namely Nuclear Physics
(CRF), Reactor Operation and Maintenance (CRO),
Services and Applications (CRA) and Neutron Activation Analysis Laboratory (CRN) constitute the
Center (CRPq).
This report presents a summary of the scientific
research and development work carried out by the
staff members and their collaborators during the period 2001-2002. The research programs include topics
in nuclear and solid-state physics, nuclear metrology,
and radiochemistry, covering both fundamental questions and applied science. Most of the programs have
strong ties to universities, other national research institutes and research laboratories. CRPq takes its
role very seriously as one of the major research reactor facility in the country providing educational opportunities to students in their programs related to
nuclear sciences. A large part of the research work
reported here had active participation of many graduate students, affiliated to the Reactor Center, working for their M.Sc. and Ph.D. degrees as well as some
undergraduate students initiating scientific activities.
Topics related with reactor operation, reactor systems
and measurements and radiation protection programs
are also covered in the present report.
The scientific programs at CRPq span several multidisciplinary, fundamental and applied research areas. Specific research programs include nuclear structure study from beta and gamma decay of radioactive nuclei and nuclear reactions, nuclear and neutron
metrology, neutron diffraction and neutron multiple-
diffraction study for crystalline and magnetic structure determination, perturbed γγ-angular correlation
(PAC) using radioactive nuclear probes to study hyperfine interactions in solids and neutron activation
analysis, both instrumental as well as involving radiochemical separation applied to the fields of health,
agriculture, environment, geology and industry. The
research in the areas of applied physics includes neutron radiography and instrumentation.
We firmly believe that no matter how much important the academic research may be in its own right,
it doesn’t do much good if it does not makes its
way to the outside world somehow. CRPq is making enormous effort to enlarge the scope of services
and applications resulting from reactor utilization so
that more and more benefits of these applications
could be offered to the society. Some of the products and services offered by the Center find their way
to petroleum industry, aeronautical and space industry, medical clinics and hospitals, semiconductor industry, environmental agencies, universities and research institutions. We produce special radioisotopes
41
Ar and 82 Br for industrial process inspection, 192 Ir
and 198 Au radiation sources for brachytherapy, 153 Sm
for bone cancer pain palliation, calibrated gamma
sources such as 133 Ba, 137 Cs, 57 Co, 60 Co, 241 Am,
152
Eu used in clinics and hospitals practicing nuclear
medicine and research laboratories, nondestructive
testing by neutron radiography, multi-element trace
analysis by NAA, irradiation of electronic grade silicon single crystals for doping with phosphorus.
Part of the research described here was carried
out in collaboration with other research institutions
and universities, both within the country and abroad.
Scientific collaborations from other departments and
centers of IPEN also contributed to our research.
These collaborations have been quite important and
contributed immensely to the development of our own
research programs. It is our firm intention to maintain and further stimulate these collaborations by offering ample access, to our laboratories, installations
and experimental facilities, to the scientists and students from other research institutions and universities.
The Radiofarmaceuticals Center at IPEN
presently imports 99 Mo, precursor of the radioisotope 99m Tc, widely used in nuclear medicine at a
considerable cost. In the year 2002 a total of about
13200 Ci of 99m Tc generators with individual kit
activities between 250 mCi and 2000 mCi, were produced and distributed to more than 260 hospitals and
clinics throughout the country, benefiting more than
2,000,000 patients.
Aiming at local production of at least a part of
99
Mo using 98 Mo(n,γ) reaction we have invested considerable effort, during the last several years, to upgrade the power level of the reactor from 2MW to
5MW. For this purpose several modifications in the
5
among the members of CRPq was conducted through
a questionnaire containing a list of 45 questions relevant to the safety aspects answered by all the reactor
staff members.
Many of our research projects received financial
support in the form of research grants and student fellowships from various external funding agencies like
Fundação de Amparo a Pesquisa do Estado de São
Paulo (FAPESP), Conselho Nacional de Desenvolvimento Cientifico e tecnológico (CNPq), International
Atomic Energy Agency (IAEA) among others. We
highly appreciate their help in our research efforts
and extend our sincere thanks for their generous financial support.
Technical and administrative support provided by
IPEN-CNEN/SP was very important and decisive for
the success of our research programs
reactor systems had to be implemented. A beryllium
irradiation element was installed in the center of the
reactor core especially for the irradiation of molybdenum. In the year 2001 ten graphite reflector elements
were replaced with the beryllium elements. A new
reactor pool water treatment and purification system
will be installed in 2003. It is further planned to increase to reactor operation schedule from the present
64 hours to 120 hour continuous per week principally
to produce high specific activity 99 Mo source.
Intense activity involving preparation of documents like Quality manual, Business and Action Plans
as well as personnel training and internal auditing
took place, consolidating the Center’s Quality management system, during 2001 and 2002. External auditing took place in December of 2002, conducted by
a team of auditors from Fundação Vanzolini. The
Center was granted BNR-ISO 9001:2000 certification
for Reactor operation and irradiation services.
In the year 2002 we also undertook the task of
implanting a safety culture enhancement program in
CRPq. A firm commitment of the higher administration of IPEN for this goal was obtained and an
assessment of the present status of the safety culture
Rajendra N. Saxena, General Manager
Research Reactor Center
IPEN-CNEN/SP
GENERAL MANAGER’S OFFICE
Dr. M.B. Vasconcellos, Head, Radiochemistry Division
Mr. R. Frajndlich, Head, Reactor Operation and Maintenance Division
Dr. A.J. Soares Head, Services and Applications Division
Dr. M.S. Dias, Head Nuclear Physics Division
Irene C. dos Santos, Administrative Assistant
Marina J.N. Mello, Administrative Assistant
6
Neutron Activation and Radiochemical Analysis
Application of neutron activation analysis to studies of
geological materials
A.M.G. Figueiredo, R. B. Ticcianelli, J. Enzweiler1
1
Depto. de Metalogênese e Geoquímica, UNICAMP, Campinas. SP, Brasil
8 hours at the nuclear reactor IEA-R1. The measurement of the induced gamma-ray activity are carried
out in a GMX20190 hyperpure Ge detector, with a
resolution of 1,90 keV for the 1332 keV gamma-ray of
60
Co. The gamma-ray spectra are processed by using
the program VISPECT, which locates peak positions
and calculates gamma-ray energies and net areas.
Trace elements, including U, Th, Ba, Sc, Rb, Ta,
Cs, Co, Hf and rare earth elements (REE), have been
extensively used in petrogenetic studies of igneous
rocks since they allow the evaluation of the main
processes involved in the generation and differentiation of melts. The development of sensitive and reliable techniques for the determination of platinum
group elements (PGE) in terrestrial materials has attracted great interest, due not only to the growing
economic importance in PGE as mineral resources,
but also to the information that these elements can
provide on metal geochemistry.
The Neutron Activation Laboratory at the Research Reactor Center of IPEN has several collaborative research programs with different Universities
(USP, UNICAMP, UFRGS), aiming the determination of trace elements in different kinds of geological matrices by INAA. In one of these collaborations, with the Instituto de Geociências, UNICAMP,
a gamma-ray spectrometer (Canberra) was set up in
Radiochemistry Division to be used by both institutions.
For the determination of REE, U, Th, and other
trace elements, the analytical procedure consists of
weighing aliquots of approximately 100 mg of the
powdered rock sample, and of geological reference
materials used as standards, in pre-cleaned polyethylene vials. Samples and reference materials are
irradiated with neutron in a flux of 1012 n cm−2 s−1 for
Several geological samples have been analyzed:
analysis of U and Th in sediment samples, in a cooperation with Universidade de São Paulo, rocks from
the Ilha do Arvoredo, Santa Catarina, in a project in
cooperation with Universidade Federal do Rio Grande
do Sul (UFRGS) and samples of turmalinites from
Quadrilátero Ferrífero, MG, in a cooperation with
Universidade de Campinas (UNICAMP).
As a part of the Quality Assurance Program of
the Neutron Activation Laboratory, we have participated in the Proficiency Test, GEOPT12- AN INTERNATIONAL PROFICIENCY TEST FOR ANALYTICAL GEOCHEMISTRY LABORATORIES,
sponsored by the Department of Earth Sciences of
the Open University, UK. The sample analyzed was
GAS serpentinite, a sample collected and prepared as
a candidate reference material by the Central Geological Laboratory, Mongolia. The results obtained were
in good agreement with the assigned consensus value,
presenting z-scores in the range -2<z<2, which means
that the results are considered to be satisfactory.
8
Determination of heavy metals in sediments for
environmental contamination studies.
A. M. G. Figueiredo, D. I. T. Fávaro, A. P. Ribeiro, F. E. Larizzatti, J. C. Wassermann2 , J. B. Sígolo3 , S.
M. B. Oliveira3 .
1
2
Laboratório de Análises e Ensaios, CTMSP, Iperó, S.P.
Departamento de Geoquímica, Universidade Federal Fluminense, R.J.
3
Instituto de Geociências, Universidade de São Paulo
Nowadays one of the most dangerous kind of pollution of aquatic systems in the Earth’s ecosystem
is resulting from heavy metals dumping. Its increasing use in industries and other activities considered
to be essential in modern human life, has resulted in
a modification of natural geochemistry cycle of these
elements, increasing their dispersion in the environment.
conditions. The statistical analysis of sedimentation
rates and age of the sediments obtained by 210 Pb reflects the associations of the samples along the core
according to the provenance of the sediments and if
they had been deposited during HLP or LLP.
2. Sediment cores from Billings Reservoir,
Rio Grande, SP The Rio Grande reservoir is located in the southeast portion of the metropolitan
area of São Paulo. It is the main water supplier of
the 4 cities and as a consequence of the soil degradation, an expressive amount of sediments has been
loading this reservoir since the beginning of its operation in 1935. In order to evaluate if the sediments
contain an historical registration of antropic activity,
three sediment cores were sampled with a piston corer
in the reservoir. The samples were analyzed by NAA
and the elements As, Ba, Br, Co, Cr, Cs, Fe, Hg,
Na, Rb, Sb, Sc, Se, Ta, Th, U, Zn, rare earth could
be determined. 226 Ra and 210 Pb were determined by
radiochemical method. The results obtained in the
first core analyzed showed a significant variation of
the concentration according to the depth for the elements Cr, Fe, Zn, As, Br, Co, Th and 210 Pb. As
for the other elements no significant variations were
observed. The concentrations of 226 Ra obtained were
higher than the values available in the literature. The
results obtained are being evaluated.
Studies of sediments from estuaries which have
been polluted by heavy metals represent the comprehension of transportation phenomena in these complex ecosystems and the discovery of the pollution history. The sediments analysis is well described in the
literature [1, 2, 3]. These studies require highly sensitive analytical techniques, with high precision and
accuracy. Instrumental neutron activation analysis
(INAA) has been used for the determination of heavy
metal distribution in sediments [4]. Six different areas
are being investigated in order to know the content
of heavy metals and other elements of interest.
1. Sediment cores from Mar Chiquita lake,
Córdoba, Argentina
The Mar Chiquita lake is the largest in Argentina
and its level has changed notably through centuries
defining high level periods (HLP) and low level periods (LLP). The purpose of the present work was to
investigate the sediment composition of the Laguna
Mar Chiquita (2 sediment cores) and del Plata (one
sediment core) by using NAA technique. The three
60 cm long sediment cores, sliced each 2 cm, were analyzed and 26 elements were determined (As, Ba, Br,
Ce, Co, Cr, Cs, Eu, Fe, Hf, La, Lu, Na, Nd, Rb, Sb,
Sc, Se, Sm, Ta, Tb, Th, U, Yb, Zn e Zr). Other complementary techniques were utilized: macroelements
(Al, Ca, Fe, K, Mg, Mn, Na, P, Si, Ti) were determined by X-ray fluorescence, and the mineralogical
composition of the sediments was determined by Xray diffraction. The results obtained did not show any
indication of anthropic contribution in the sediment
composition, and concentration of the majority of the
elements analyzed is uniform along the entire profile
of the analyzed core. Cluster analysis of elemental
concentrations reflects that in Laguna del Plata the
fine fractions of the sediments is dominated by detrital minerals, while in the Laguna Mar Chiquita, the
neoformed minerals are the principal components. In
both lakes, it was possible to identify compositional
variations in the sediment segments, which may correspond to temporal fluctuations in the sedimentation
3. Sediment analysis from a lagoon of the
Wastewater Treatment Plant in Barueri, SP
The Sewage Treatment Plant (STP) in Barueri, São
Paulo, processes a significant part of the sewage generated in São Paulo city. Due to economic and technical problems, the residual sludge produced in the
Barueri plant, from 1988 to 1996, were cumulatively
disposed over the land, in piles and in open areas,
resulting in about 215000 m3 of residues, disposed
directly on the soil. The STP has two ponds, which
were built to landscape the place. INAA was used to
determine metals (Ba, Co, Cr, Cs, Fe, Hf, Mo, Rb,
Sc, Ta, Zn), semi-metals (As, Sb, Se), actinides (U,
Th) and rare earth elements (La, Ce, Nd, Sm, Eu,
Tb, Yb and Lu) in bottom sediments from one of
the ponds, in order to verify whether it was contaminated due to the waste generated by the plant. The
results obtained were compared to the concentration
determined in a soil profile and in a sample of rock in
natura, representing the lithologies of the region, and
showed a homogeneous distribution of the elements
along the pond and indicated that only As, Cr and
9
Zn can have their origin associated with the residues
disposed around the pond.
4. Sediment samples from Lagoa da Viração, Fernando de Noronha, RN Fernando de
Noronha is an isolated group of 21 volcanic islands
located in the South Equatorial Atlantic at 03o 51’
South and 32o 25’ West, approximately 215 miles
from Cape São Roque in the state of Rio Grande
do Norte. Geological studies indicate that the volcanic archipelago emerged around 12,300,000 years
ago. This archipelago is a protected and isolated
habitat, with restrict access and almost no evidence
of anthropic contamination has been observed there.
Viração Lagoon is a small lake located at Fernando
de Noronha Island and it is an endorheic region situated 20 meters above the sea level, being an unusual
freshwater environment considered as quaternary sedimentary systems existent in other oceanic South Atlantic Islands. The local drainage is restricted and
ephemeral, and no connection with the general insular drainage is observed. As a preliminary study of
this environment, a project was established to detect
and to analyze significant changes in a habitat that
is protected and isolated. For this purpose, one core
sediment, 52-cm long, was extracted in 2000, in the
Viração lagoon, at a water-depth of 1m, to determine
metals and sedimentation rates. These samples were
analyzed by NAA to determine elements As, Ba, Br,
Co, Cr, Cs, Fe, Hg, Na, Rb, Sb, Sc, Se, Ta, Th, U,
Zn and rare earths. Ce, Eu, La, Lu, Nd, Sm, Tb and
Yb. The majority of the elements and rare earths
analyzed showed concentrations slightly higher when
compared with shale values, probably due to volcanic
origin of the archipelago.
5. Distribution of metallic elements in river
sediments from Parque Estadual da Ilha Anchieta, SP The aim of this work is to study the geochemical behavior of metals in river sediments from
Parque Estadual da Ilha Anchieta which is located
in the northern coast of São Paulo. The Anchieta
Island presents many natural ecosystems well preserved without anthropogenic contamination. The
sediments were collected in two different points in
one of the main rivers of the island. Samples were
analyzed by instrumental neutron activation analyses
(INAA) which permits the quantification of total concentration of metals (Ba, Co, Cr, Cs, Fe Hf, Rb, Sc,
Ta and Zn), rare earth elements (Ce, Eu, La, Lu, Nd,
Sm, Tb e Yb), actinides (U and Th) and non metals
(As, Br and Sb). Elemental content in the samples
had remained relatively constant along the depth of
the sample and the changes seemed to be well correlated with the size of the particles in the samples.
The precision and the accuracy of the results were
evaluated by the analysis of two geological reference
materials and data obtained were in good agreement
with recommended values. The values obtained for
the analyzed elements can be considered the natural
concentration of those elements, since Parque Estadual da Ilha Anchieta
is preserved from anthropogenic impact.
6. Behavior of trace elements in sediment
cores from Ilha Grande, RJ The present work
aims to identify atmospheric and marine inputs of 9
metals (Ba, Co, Cr, Cs, Fe, Hf, Rb, Sc, Zn), 8 rare
earths (La, Ce, Nd, Sm, Eu, Tb, Yb e Lu), 2 actinides
(U, Th) and 3 non-metals (As, Sb, Se) in sediment
cores from a remote area, the Biological Reserve of
Praia do Sul, Ilha Grande, Rio de Janeiro. The sediment cores were sampled in a peat bog (out of the
tidal reach) and in a mangrove, downstream of the
peat bog. The analytical technique employed was
INNA. A preliminary sediment dating with Po-210
was also carried out by applying radiochemical procedures and measurements were done in an Alpha
spectrometer The results indicate that the peat bog
core present a slight surface enrichment that can be
attributed to atmospheric inputs. Increasing concentrations of metals with age is probably due to the
history of soil occupation. In the mangrove core, no
significant increase in concentration could be detected
in the surface sediments (except for Zn) confirming
the suitability of the peat bog core as a tracer for
atmospheric inputs
References
[1] B.J. Presley, J.H. Trefry, R.F. Shokes. Water, Air
and Soil Pollut., 13 (1980) 481.
[2] U. Forstner, W. Salomons. Environ. Tech. Letters,
1 (1980) 494.
[3] U. Forstner, G.T.W. Wittman, Metal Pollution
in the Aquatic Environment, Springer Verlag,
Berlin, 486p., 1983.
[4] W.D. Ehmann, S.W. Yates, Anal. Chem. 60
(1988) 42R.
[5] D. M. Krohling, M. Iriondo, Quaternary International 57/58 (1999) 149.
10
Determination of platinum group elements and gold in
reference materials by instrumental neutron activation
analysis and inductively coupled plasma-mass
spectrometry with nickel sulphide fire-assay collection.
A.M.G.Figueiredo , C.P.R.Morcelli, J.E.S Sarkis1 , M.Kakazu
1
1.
, J.Enzweiler2
Laboratório de Caracterização Isotópica, Instituto de Pesquisas Energéticas e Nucleares
2
Instituto de Geociências, UNICAMP, Campinas, São Paulo, SP, Brasil
tion has been used as a mean of analyzing PGE, with
the main advantage of avoiding problems of losses
of PGE during the HCl digestion of the NiS button.
Buttons were prepared by mixing the sample (10-15g)
with nickel and sulfur fluxes in a fire clay crucible and
fused at temperatures around 1000o C. The ICP-MS
analysis were performed with an HR-ICP-MS Instrument, Element, Finnigan MAT. For NAA, the filters
containing the PGEs and Au were irradiated at the
nuclear research reactor IEA-R1 at IPEN. The measurements of the induced gamma-ray activity were
carried out in an hyperpure Ge detector.
The natural abundance of Platinum Group Elements (PGE) Ru, Rh, Pd, Os, Ir, Pt and Au is very
low (ng g−1 or sub ng g −1 ) and the usual methods
for the determination of these elements in geological samples consist of a pre-concentration procedure
followed by detection using a high sensitive analytical technique. The NiS fire assay, used as a collector to concentrate all noble metals, is a classical preconcentration method due to the possibility of using
large samples, eliminating problems of heterogeneous
distribution in geological matrices.
In this work, Instrumental Neutron Activation
Analysis (INAA) and Inductively Coupled PlasmaMass Spectrometry (ICP-MS) after NiS fire assay
were used to determine PGE and Au in the geological reference materials peridotite GPt-3 and pyroxene peridotite GPt-4 (IGGE, China). INAA has
been one of the most useful analytical techniques for
PGEs and Au determination, due to its high sensitivity and accuracy. After the fire assay, the NiS
button is dissolved in concentrated hydrochloric acid,
leaving a residue of insoluble PGE sulfides. The solution is filtered and the filter is directly irradiated
with neutrons. In more recent years, ICP-MS with
nickel fire assay collection and tellurium coprecipita-
In general, the results obtained by both techniques
were in good agreement with recommended values.
INAA results exhibited higher values than the recommended values for Pd and Pt in GPt-3, while the opposite effect was observed for sample GPt-4. Ru was
not detected by INAA. On the other hand, Rh and
Ir were determined more accurately by INAA (relative errors better than 10%). The ICP-MS analytical
technique showed better detection limits, and all the
PGE were determined. Results obtained for Pt and
Pd presented accuracy better than 5% while losses
were observed for Os and Ir.
11
Determination of trace elements elements in Tillandsia
usneoides by neutron activation analysis for
environmental biomonitoring
A.M.G. Figueiredo, C.A. Nogueira, M. Saiki, R.B. Ticianelli, M. Domingos1
1
Instituto de Botânica, São Paulo, SP, Brasil.
Bioindicators may be defined as organisms which,
submitted to environmental alterations, may change
their vital functions or chemical composition, making
possible the evaluation of environmental impact extension [1]. The use of bioindicators may be of great
applicability, providing rapid and accurate information for the evaluation of environmental changes due
to anthropic activities. Plants as bioindicators are a
good alternative to conventional pollution control instrumentation. Several advantages are observed: different contaminant control in large areas, possibility
of usage in different sites at the same time, low plant
cultivation and maintenance cost, short-term effect
evaluation after exposition (from hours to a few days)
when plants of short life cycles are used, plant exposition in situ in different environmental conditions
allowing the evaluation of soil, water and atmosphere
contamination.
Paulo (CETESB), the government air quality control
agency, daily emissions from about 5.5 million motor
vehicles are the main sources of air pollution in the
city. The quantity of suspended matter released into
the atmosphere of the extended city, which consists
of the city of São Paulo and the cities that surround
it, is estimated in 64100 tons[7].
The government air quality control agency
CETESB operates an automatic network, in São
Paulo, with 23 monitoring stations. In this study,
ten exposure sites were chosen to transplant the samples of Tillandsia usneoides, being seven in the city of
São Paulo and three in the greater São Paulo (Santo
André, São Caetano e Mauá), having different levels of pollution. These sites were chosen because of
the information about other air quality parameters
provided by CETESB about these areas. The unpolluted area chosen to collect the Tillandsia usneoides
was a small farm in Mogi das Cruzes, located about
70 km from São Paulo, with a low industrial and traffic influence, making it adequate for transplantation
experiments. Active biomonitoring, which consists
of transferring plants collected from unpolluted sites
to the area to be monitored, was employed. This
methodological approach is adopted because, in polluted or urban sites, the vegetation is frequently absent. Each sample for exposure was composed of 5 g
of plants, tied by teflon strings to a gyrator apparatus (6 samples per apparatus), which turned with the
wind so that homogenous contact with air contaminants was guaranteed. The samples of Tillandsia usneoides were submitted to exposure for 8 weeks and,
after the exposure time, the samples were separately
frozen without washing and stored at - 20o C until
analyses Samples were dried at 40o C in a ventilated
oven until reaching constant weight and then ground
in a blender with Ti knifes. After this procedure, the
samples were ground and homogenized manually in
agate mortars. 200mg of the samples were accurately
weighed in polyethylene envelopes, previously cleaned
with diluted nitric acid solution.
There are several species that can be used as
bioindicators of atmospheric pollutants. The epiphytic lower plants such as lichens and mosses have
been widely used as indicators of regional air quality in several European countries[2]. The epiphytic
bromeliad Tillandsia usneoides L. has also been used
as an air quality monitor [3]. Epiphytic plants are
efficient air pollution biomonitors, because they have
no contact with soil, taking out nutrients from the
atmosphere. Their tissue content largely reflects atmospheric contamination. In general, they are excellent accumulator biomonitors.
Tillandsia usneoides L. is an aerial epiphytic
bromeliad that lives on trees or other kinds of inert subtracts, absorbing water and nutrients directly
from the environment. Due to its morphological
and physiological characteristics this species accumulates the pollutants present in the atmosphere.
This species is well adapted to dry and hot regions,
and have been used as a bioindicator in tropical areas. Because of its characteristics, some authors, including Arndt & Schweizer[1] and Markert et al.[4],
have suggested the universal use of T. usneoides as
a metal accumulator. In Brazil, Tillandsia usneoides
was demonstrated to be a suitable biomonitor for atmospheric mercury contamination[5, 6].
Standards of the elements of interest were prepared
by mixing appropriate aliquots of solutions of these
elements made from spectroscopically pure reagents
or from SPEX standard solutions. Aliquots of these
solutions were pipetted onto 1 cm2 pieces of Whatman No. 40 filter paper, evaporated to dryness under an infrared lamp, and sealed in polyethylene envelopes, similar to those used in the preparation of
the samples. About 200mg of the biological standard
There are serious air pollution problems in São
Paulo city, which is an important industrialized and
economic center of Brazil, having a population of
around 18 million people. The city is subjected to
frequent thermal inversions. According to the Environmental Protection Agency of the State of São
12
about 5 km from the monitoring site. This fact will
be further verified in temporal and seasonal monitoring. The results obtained for rare earth elements, Al,
Fe, Mg, Mn, Rb and Sc indicate mineral dust origin.
The elements Ba, As and Sb presented higher values
than those found in the control site in the station near
the airport and in Parque D. Pedro, which may be
attributed to diesel engines (vehicular sources) since
these stations present high levels of SO2 and NO2 [7].
The results obtained demonstrated a promising potential of Tillandsia usneoides as a metal accumulator
in urban areas, indicating its usage as a biomonitor
which may provide relevant information about metal
pollution in the city of São Paulo.
reference material Orchard Leaves (NIST SRM 1571)
and of the geological reference material Soil-7 (IAEA)
were weighed and prepared similarly to the sample.
For the determination of Al, Ti, V, Cl, Mg and Mn,
samples and standards were irradiated for 5 minutes
in a thermal neutron flux of 4x1011 cm−2 s−1 , at the
IEA-R1 nuclear research reactor at IPEN. For the
other elements (As, Ba, Br, Co, Cr, Fe, K, Mo, Na,
Rb, Sb, Sc, Th, Zn, and the rare earths La, Ce, Nd,
Sm ,Eu, Tb and Yb), samples and standards were
irradiated for 16 hours at a thermal neutron flux
of 1x1013 cm−2 s−1 . The measurements of the induced gamma-ray activity were carried out using a
GMX20190 hyperpure Ge detector. The multichannel analyzer was a 8192 channel Canberra S-100 plugin-card in a PC computer. The energy resolution of
the system was 1.90 keV (FWHM) for the 1332 keV
gamma-ray of 60 Co. For the 5 minute irradiation, decay and counting times were each 3 minutes. Two
series of measurements were performed after the 16
hour irradiation; the first was done from 5th-7th days
after irradiation and the second one after 15-20 days
of decay. Counting times ranged from 3 to 10 hours.
The gamma-ray spectra were processed by using an
in-house gamma-ray software, VISPECT[8], which locates peak position and calculates the energies and
net areas. The accuracy and precision of the method
was previously determined by analyzing the biological reference material Orchard Leaves NIST SRM
1571[9]. The method showed accuracy and precision
better than 15 % for most elements.
The data obtained showed that the control site
presented lower concentration for most elements analyzed and the highest concentrations of Na, Cl, Br,
K. The highest concentrations of Zn, Cu and V were
observed in Santo André, an industrial city around
São Paulo, and Parque D. Pedro, downtown. These
metals are used in lubricating oils, and the high values observed may be associated to industrial and vehicular sources in these sites, as the region of Santo
André has about 200 steel companies and, according
to CETESB, Parque D. Pedro presented acceptable
levels of NO2, in 2000, in only 46.9% of days (in 152
days)7 . The emission of NO2 is mainly related to automotive vehicles emissions. On the other hand, Co
showed a spot of concentration in São Miguel, which
might be associated to a metal industry located at
References
[1] U. Arndt., B. Schweiger.. The use of bioindicators for environmental monitoring in tropical and
subtropical countries. In: Ellenberg et al. Biological monitoring. Signals from the environment.
Vieweg. Eschborn, 1991, pp. 199-298.
[2] U. Herpin, J. Berlekamp, B. Markert, B. Wolterbeek, K. Grodzinska, U. Siewers, L. Lieth, V.
Weckert, Sci. Total Environ., 187 (1996) 185.
[3] D.H. Benzing, D. Bermudes, Selbyana, 21 (1991)
46.
[4] B. Markert, U. Herpin, J. Berlekamp, J.
Oehlmann, K. Grodzinska, B. Mankovska, I.
Suchara, U. Siewers, V. Weckert, H. Lieth, Sci.
Total Environ., 193 (1996) 85.
[5] C.F. Calasans, O. Malm, Sci. Total Environ., 208
(1997) 165.
[6] G.M. Amado Filho, L.R. Andrade, M. Farina, O.
Malm, Atmospheric Environment 36 (2002) 881.
[7] CETESB, Relatorio de qualidade do ar no Estado
de São Paulo – 1998. Série Relatórios, 2000.
[8] D.Piccot, personal communication, 1989.
[9] A.M.G. Figueiredo, M. Saiki, R.B. Ticianelli,
M. Domingos, E.S.J. Alves, B. Markert, J. Radioanal. Nucl.Chem.,249(2001)391
13
Characterization of Brazilian prehistoric ceramics
C. S. Munita, A. Nascimento1 , R.P. Paiva, S.B. Schreiber, S. Luna1 , P.M.S Oliveira2
1
2
Núcleo de Estudos Arqueológicos, UFPE, PE,
Departamento de Matemática e Estatística, USP
This project is part of an archaeometry program at
the Neutron Activation Analysis Laboratory – LAN
at CRPq. In the last six years, instrumental neutron
activation analysis has been applied for the analysis of ceramics of archaeological sites from several
states: São Paulo[1], Minas Gerais[2], Pernambuco
and Amazonas in collaboration with various archaeologists. The archaeometry community from different
universities of the country has responded enthusiastically to this program and we expect this research to
grow rapidly.
In our laboratory the sample preparation is made
by cleaning the ceramic fragment with tungsten carbide rotary file attached to the end of the flexible shaft
of a variable speed drill. Four or five holes are drilled
as deep into the core of the sherd as possible without
drilling through the walls. The powdered samples are
dried in an oven at 100 o C for 24 h. Neutron activation analysis procedure at LAN for this program
consists of four stages:
is important to determine as many elements as possible to differentiate between chemical groups (i.e., geographical source areas). Comparisons between source
areas in different regions will not necessarily use the
same elements for the most effective separation. One
never knows a priori which elements will work best.
Elements that work well in one region may be unsuccessful in another region.
The quantitative analysis at LAN uses the log base
10 for concentrations. There are two reasons for this
preference. First, for trace elements the data appear
to be more normally distributed when treated as logarithms of the measured concentrations, the second
reason is that transformation of concentration data
into logarithms compensates for the differences in the
magnitudes between the major elements, such as K,
Fe, and the trace elements, such as the REE. Thus,
transformation to log effects a quasi standardization
that facilitates the application of multivariate methods.
Frequently the statistical interpretation data in
our group is made using three multivariate analyses: cluster analysis, principal components analysis and/or discriminate analysis. Cluster analysis
is based on a dissimilarity matrix in which the distances between all pairs of elements are calculated
using one of several possible distances measured; we
use the squared-mean Euclidean distance represented
in a dendrogram as an initial step in the identification of groups. In principal components analysis the
transformation of the data set is based on eigenvector
methods to determine the direction and magnitude of
maximum variance in hyperspace. However, canonical discriminant analysis extracts a new set of variables that maximizes the differences between two or
more groups rather than maximizing the total variance of the data set. It is based on the assumption
that the pooled variance-covariance matrix is an accurate representation of the total variance and covariance. It is assumed that all elements in the data
necessarily belong to one of the known groups.
During the years 2001/2002 were analyzed 80 samples from 6 archaeological sites (Justino, Alcobaça,
São José I and II, Vitória Régia I and II), located in
the Brazilian Northeast. Our results were compared
with petrographic studies already made in the samples. Based on petrographic observation clays contains at least 5-35 % clay minerals i.e., at leats onehalf to two-third of the matrix comprises clay minerals. The chemical data showed that the pastes are
relatively low in Ca, Fe, and K; the bulk of these elements must be contained within the rock fragment
and mineral phases. The dominant clay minerals are
• About 100 mg of ceramic samples and two standards (Buffalo River Sediment -NIST-SRM2704, and Coal Fly Ash -ICHTJ-CTA-FFA-1)
are weighed in polyethylene bags and involved
in Al foil.
• Groups of 6 samples and one of each reference
material are packed and irradiated in the swimming pool research reactor, IEA-R1, in a thermal neutron flux of about 5 x 1012 n cm−2 s−1
for 8 h.
• As, Ba, K, La, Lu, Na, Nd, Sm, and YB are
measured after 7 day cooling time.
• Ce, Cr, Cs, Eu, Fe, Hf, Rb, Sb, Sc, Tb, Th, Zn
and U are measured after three or four weeks.
Normally the interference of 235 U fission in the determination of La and Ce is negligible because U concentration is less than 5ppm and the REE concentrations are not too low[3]. The main components of the
clays (i.e., Al2 O3 , SiO2 and water) that are typically
present in amounts greater than 5%, minor impurities such as the oxides of Ca, Fe, K, Mg, Na, and
Ti are present in amounts between 1.000 ppm to 5%.
However, it is the trace constituents, elements at concentration below 1.000 ppm, whose presence in clays
is effectively accidental that provide the primary basis for provenience analysis. It is reasonable to anticipate that a more complete analysis, especially one
that determines the trace elements constituents, will
increase the likelihood of success when utilizing chemical characterization for source determination. Also it
14
kaolinite and halloysite, which lack cations such as
Ca, Fe and K, and are the expected products of soil
formation on volcanic parent materials under tropical
climate conditions.
3
4
2
3
3
5
6
5
1
3
PCO2
6
3
5
3 4 4 2 1
55
4
3
5
3
3
-1
6
5
6
23
5
4
5
1
44
2
3
6
1-São José I
3
4
-2
1
4
1
2 5
4
3
1
5 5 6 4 44 5
5
3
6
3 5 4 2
2
6
3
4
0
4
4
4
2-São José II
4 4
4
3-Justino
4
4-Alcobaça
5-V. Régia I
-3
6-V. Régia II
-3
In order to examine questions of exchange and socio political interaction among the prehistoric cultures of these six sites, the similarities among samples were studied by means of principal omponent
analysis. Since differences in chemical composition
are typically interpreted as evidence for distinct production locations, our main purpose was to identify
and distinguish the similarities among the samples
analyzed with the aim to define one or more compositional groups. A bivariate plot of two first principal
components is presented in Fig. 1. As can be seen,
the samples of each site form a very tight chemically
homogeneous group, showing a high degree of chemical similarity among them. The results showed that
clay from ceramics fragments collected and analyzed
from six sites were originated from the same raw material.
-2
-1
0
PCO1
1
2
3
Figure 1: Plot of the principal component 2 versus
principal component 1.
References
[1] C.S. Munita, R.P. Paiva, M.A. Alves, E.F. Momose, M. Saiki. J. Radioanal. Nucl. Chem. 2000,
244(3), 575-578.
[2] C.S. Munita, R.P. Paiva, M.A. Alves, P.M.S.
Oliveira, E.F. Momose. J. Trace Microprobe
Techn. 2000, 18(3), 381-387.
[3] C.S. Munita, R.P. Paiva, M.A. Alves, P.M.S.
Oliveira, E.F. Momose. J. Radioanal. Nucl. Chem.
2001, 248(1), 93-96.
15
Evaluation of Mercury, MethylMercury and other elements
of interest in fish, hair and diets of pre-school children
from Amazonic region.
Luciana A. Farias, Déborah I.T. Fávaro, Marina B.A. Vasconcellos, Lucia K. Yuyama1
1
Coordenação de Pesquisas em Ciências da Saúde /CPCS – INPA, Manaus, Am.
The presence of mercury (Hg) in the food chain
and its absorption by humans is universally recognized as a potential health hazard. Once Hg is released into rivers, lakes and other aquatic environments, bacteria can transform the Hg into its organic
form – highly toxic methyl mercury (Me-Hg). In this
form it can be absorbed by the aquatic fauna, in increasing concentration (biomagnifying) as it moves
up the food chain to fish and then to humans. People living in the Amazon region suffer from mercury
poisoning resulting from the consumption of contaminated fish[1, 2, 3, 4].
U can be determined as well. The diets proximate
composition will be determined according to AOAC
methodologies. The daily dietary intake for Hg, MeHg and other elements will be calculated and compared to the new recommendations (DRI-NRC)[7].
All these data will be used to make a nutritional
and toxicological assessment of the population in the
present study. Correlation between Hg and Se values
will be investigated as well. This project is being carried out in collaboration with researchers from INPA,
responsible for sampling and results interpretation.
For years, mercury used in gold mining was thrown
into the rivers. As a consequence people who live
along those rivers and depend on fish for a major
part of their diet have relatively high levels of Hg in
their hair (an indication of mercury exposure). These
people have two different ways of Hg exposure: direct exposure to Hg vapor (inorganic Hg) and indirect exposure due to fish consumption containing
Me-Hg. The purpose of the present work is to develop and validate methodologies for determination
of total Hg and methyl mercury by using cold vapor/ atomic absorption spectrometry technique, in
different kinds of matrices[5]. Fish, hair and diet
samples from pre-school children, exposed to Hg contamination in Jaú National Park, Amazonic region
will be analyzed. Children are a risk group and
are more vulnerable to mercury and methyl mercury
contamination[6].Toxicological evaluation related to
Hg and Me-Hg levels in these samples will be performed and the levels compared to limits established
by WHO and Brazilian legislation, in case of fish mercury limits. By using NAA technique the content of
some mineral elements such as Ca, Cl, Fe, K, Mg, Mn,
Na, Se and Zn , elements nutritionally important, will
be determined in fish and diet samples. Other trace
elements such as As, Ba, Co, Cr, Cs, Rb, Sc, Th and
References
[1] S. Hacon, E.R.R. Rochedo, R.R.R. Campos, L.D.
Lacerda . J. Geochem. Expl., 58(1997)206.
[2] A.A.P. Boischio, H. Henshel. Environ. Res., Section A, 84 (2000)108.
[3] E.C.O. Santos, I.M. Jesus, E.S. Brabo, E.C.B.
Loureiro, A.F.S. Mascarenhas, J. Weirich, V.M.
Camara, D. Cleary. Environ. Res., Section A, 84
(2000)100.
[4] H. Akagi, O. Malm, Y. Kinjo, M. Harada, F.J.P.
Branches, W.C. Pfeiffer, H. Kato. Sci. Total Environ., 175 (1995) 85.
[5] Horvat, M. (1996).”Mercury Analysis and Speciation”. In Environmental Samples in Global and
Regional Mercury Cycles: Sources, Fluxes and
Mass Balances, p. 1-31, W. Baeyens et al (eds).
[6] National Research Council. Toxicological effects
of Methylmercury, 2000, National Academy of
Press.
[7] National Research Council. Dietary Reference Intakes, 2000, 2001. National Academy of Press.
16
Neutron activation analysis applied to the determination
of chemical composition of metallic materials
E. G. Moreira, M. B. A. Vasconcellos, M. Saiki, C. O. Iamashita1
1
Divisão de Química, Instituto de Pesquisas Technologicas (IPT)
The chemical composition of metallic materials
plays an important role in the technological properties of these materials. Mechanical properties, corrosion resistance, temperability and other properties
may be enhanced by the addition of suitable amounts
of different elements to the materials. It is also important to control the impurities from the manufacturing
process, which could influence the characteristics of
the material negatively[1].
Many analytical techniques have been used in the
study of the chemical composition of metals and
their alloys, such as atomic absorption spectrometry,
x-ray fluorescence spectroscopy, ICP spectroscopy,
ionic chromatography and neutron activation analysis. The instrumental neutron activation analysis
technique, INAA, has the advantage, over some of
these techniques, to provide precise and accurate results, not only for the major and minor constituents
but also for trace elements, without the difficulties
arising in the process of sample dissolution and/or element separation prior to analysis. The contribution
to the metallic materials composition determination
by INAA was accomplished in the following studies:
1. Analysis of iron and steel samples by
INAA
The purpose of this work was to optimize the
INAA technique in the study of the chemical composition of iron and steel samples in the Activation
Analysis Laboratory ( LAN), at the research reactor
center of IPEN. For this purpose the iron and steel
certified reference materials (CRM) were analyzed to
assess the suitability of the method. Possible interference in the INAA technique were also investigated. It
was concluded that there is no need for interference
corrections for the elements analyzed. The method
was applied to the analysis of industrial iron and steel
samples. Applying the comparative method of INAA,
As, Co, Cr, Cu, Mn, Mo, Ni, V and W were determined in reference materials and samples after short
and long irradiations, according to element half-lives.
Induced radioactivity was measured by gamma ray
spectrometry.
2. Analysis of silicon and ferrosilicon reference materials and silicon candidate reference
material by INAA
Silicon has many industrial applications; for instance, it is used as a precursor in the production of
silicon derivatives. Control of the chemical and structural characteristics of silicon must be attained as it
influences the process of production of the derived
materials[2].
The chemical division at IPT set out a new silicon reference material development program as the
existing reference materials are old and do not accomplish the present specifications of Brazilian producers.
INAA was used at the Neutron Activation Analysis
Laboratory, in the development of this new material, evaluating possible sample contamination from
the grinding machines; and the variation in sample
composition due to granulometry.
After the new reference material was packed, its
intra-bottle and between bottles degrees of homogeneity were determined by means of INAA of Mn
for a suitable amount of bottles, assuring that the
CRM is homogenous for its intended use.
The comparative method of INAA was also used
in the determination of 21 elements in silicon and
ferrosilicon reference materials and in the silicon candidate reference material.
References
[1] V. Chiaverine, Aços e Ferros Fundidos, 5. ed., São
Paulo, ABM (1982).
[2] J. I. Korschwitz, M. Home-Grant (Eds.), KirkOthmer Encyclopedia of Chemical Technology, 4.
ed., New York, Wiley (1997).
17
Biomonitoring of toxic metals in marine organisms in the
Coast of São Paulo by neutron activation analysis and
atomic absorption spectroscopy
M.G.M.Catharino , M.B.A Vasconcellos , M.Saiki , D.I.T. Fávaro
Coastal regions in many parts of the world have
been for a long time, suffering severe impact from
industrial and agricultural activities, causing serious
concern to health and environmental authorities as
to the effects to the fauna and to the populations of
these regions. These concerns call for the need for
effective monitoring program, aimed at assessing the
quality of the waters and of the degree of pollution encountered, by means of analysis of marine organisms
and sediments, as well as the analysis of the water
itself.
rubidium, cadmium, barium and lead, in the soft tissue of the blue mussel, Mityllus edulis, in seven different sites of the Limfjorden, in Denmark. The mussels
in the different sites could be distinguished by means
of principal component analysis. The comparison of
the levels of trace elements found in the mussels, in
relation to the levels of 1982, has shown that the contamination with trace elements in the regions studied
has increased in the last 15 years. From the data
obtained, it was concluded that the blue mussel is a
good indicator for the identification of coastal areas
exposed to metallic contaminants.
In Brazil, due to the extension of the coast and
to the innumerous pollution problems encountered in
several regions, it is necessary to obtain a large volume of data for the monitoring of many environmental compartments, such as water, soils, sediments and
biomonitors. The aim of this project is to give a contribution to the biomonitoring of some regions of the
coast of the State of São Paulo, by using the bivalve
Perna perna, which is commonly found in the whole
Brazilian coast and is consumed by the population,
in an amount estimated in seven tons per month, in
São Paulo. Due to its sedentary habits and its ability
to concentrate many pollutants, the Perna perna is
being used in the studies of evaluation of the quality
of coastal waters. The project will be conducted in
collaboration with the Oceanographic Institute of the
University of São Paulo.
For the utilization in the experiments, healthy animals have to be obtained, collected in regions far
away from sources of pollution. The organisms to
be utilized in this project will be acquired in a cultivation site situated in the Castelhanos Beach,in Ilha
Bela, an isolated beach which is difficult to be acessed
by tourists. The organisms will be transplanted at
several points along the coast, from São Sebastião
to Santos. The sites chosen in Santos are strategic
in the sense that they monitor the Bay of Santos,
in relation to industrial emissions and to the emissary of SABESP. Every three months, the organisms
will be removed from the transplant points and their
enzymatic activity will be measured, in the Oceanographic Institute. The analysis of trace elements will
be carried out at the Neutron Activation Analysis
Laboratory, at IPEN/CNEN-SP, using two analytical techniques: neutron activation analysis (NAA)
and atomic absorption spectroscopy.
By using a suitable combination of irradiation and
measuring times, it is possible to determine, by NAA,
elements such as: Cl, Cu, I, Mg, Mn, Ti, V ,As, Ba,
A tragic case of marine pollution was the contamination of the Minamata Bay, in Japan, in the 1950’s
and 60’s, when the Chisso Company, a producer of
acetaldehyde, was responsible for discharging mercury and methyl mercury, which entered the food
chain, causing the death or incapacitation of thousands of people, as a consequence of the later called
“Minamata Disease”[1]. In order to better understand
and prevent whenever possible the occurrence of such
regrettable events, in 1976, in the US, the “Mussel
Watch Programme” was started, aiming at utilizing
the so-called “sentinel organisms” like mussels (Mytillus) and oysters (Ostrea or Cassostrea) for the biomonitoring of coastal areas. Several other countries
have also started programmes of this kind[2].
The main inorganic elements of interest to this
kind of program are the ones considered most potentially toxic, such as: mercury, lead, cadmium, arsenic,
nickel, copper, zinc, antimony and others. Besides the
inorganic components, the determination of organic
components is also very important, such as PCBs and
PAHs. In several studies, besides the analysis of toxic
elements in the marine organisms, the mechanisms of
incorporation of these elements and the influence of
several physico-chemical parameters are studied, using radioactive isotopes. Chong and Wang[3] studied the assimilation of cadmium, chromium and zinc
by the bivalves Perna viridis and Ruditapes philippinarum, which are commonly used as biomonitors
of coastal contamination in tropical and subtropical waters. The authors determined the efficiency
of assimilation of three cited elements, in the marine organisms by feeding them with different species
of phytoplankton. The study demonstrated that the
organisms are capable of accumulating metals from
the food ingested and that the type of food seems
to have different effects in the assimilation of metals from the different kinds of bivalves. Bechmann et
al.[4] determined the concentrations of the elements
vanadium, chromium, cobalt, nickel, copper, gallium,
18
Br , Ca, Cd, Co, Fe, Hg, Mo, Na, Sb, Sc, Se, REE
elements. By atomic absorption spectroscopy the aim
is to determine mainly: Hg (CVAAS), lead, which is
not possible to determine by NAA, cadmium and selenium. The speciation of mercury, namely determination of methyl mercury, in the marine organisms,
will be carried out by CVAAS, using a method of
separation of organic and inorganic species of mercury based on ion exchange, followed by destruction
of methyl mercury by UV radiation or acid decomposition.
Fukuoka: Kyushu University Press (1999).
[2] A. Viarengo; I. Canesi. Mussel as biological indicators of pollution. Aquaculture 94(1991)225.
[3] K. Chong; W.X. Wang. Assimilation of Cd, Cr
and Zn by the green mussel Perna Virides and
the clam Ruditapes philippinarum. Environmental Toxicology and Chemistry, 19(2000)1660.
[4] I.E. Bechman; S. Sturup; L.V. Kristensen. High
resolution ICP-MS determination and multivariate evaluation of 10 trace elements in mussels from
seven sites in Limfjorden, Denmark. Fresenius
Journal of Analytical Chemistry, 368(2001)708.
References
[1] T. Takeuchi; K. Eto. The pathology of Minamata Disease – A tragic history of water pollution.
19
Biomonitoring of air pollution through trace element
analysis in Canoparmelia texana and Tradescantia
plant species
M. Saiki, A. Fuga, E. R. Alves, M.B.A. Vasconcellos, N.M. Sumita1 , P.H.N. Saldiva1 , M.P. Marcelli2
1
Laboratoryy of Experimental Air Pollution, Medical School of São Paulo University, São Paulo,
2
Botanic Institute, Seção de Micologia e Liquenologia, São Paulo, SP
Pollution increase in environment has led to experimental methods optimization to evaluate contaminant levels and to identify its source. In this context, several plant species have been extensively investigated to use them as biomonitors of toxic elements. Among several types of plants of our ecosystem, Canoparmelia texana and Tradescantia pallida species were chosen for atmospheric air pollution
study in different locations of the São Paulo city.
in lichen samples from non-polluted area were compared from those obtained in lichen samples collected
at IPEN. The mean values obtained for Co, Cr, Fe,
La, Na, Sb and U were significantly higher in samples from IPEN and for the elements As, Ca, Cl, K,
Rb, Se and Zn, there were no differences. Results obtained for As, Co, Cr, Fe, La, Mn, Sb, U and Zn in
C. texana are presented in Fig.1.
The biomonitor C. texana chosen in this investigation is an epiphytic foliose lichen tolerant to pollution. It is one of the most widely spread lichenized
fungi species in open places of natural primary and
secondary vegetal formation as well as inside cities
all over the Brazilian territory except on the coastal
cities. This species was collected from the bark trees
in non-polluted sites of Ibiuna town, about 100 km
from São Paulo city and Itapetininga region, located
in Atlantic Forest and Manuel Botelho Park, both
located at São Paulo State. 36 lichen samples were
collected at IPEN, located inside Campus of the University of São Paulo. T. pallida (Rose) D.R. Hunt.
cv. purpurea Boom is a higher plant from Commelinaceae family was chosen since it is easily sampled,
cultivated and propagated. It is an ornamental plant
found in gardens and even in places with high pollution levels like streets and avenues. Besides, in recent
years Tradescantia plants have become widely known
for the detection of clastogenic effects of heavy metal
ions by micronucleus assay and it is suggested to biomonitor metal-contaminated soils[1]. The nuclei of
plant (DNA molecules) that are submitted to high
pollution levels are split in micronuclei so that T.
pallida might be used as an environmental pollution
indicator.
10000
non-polluted
Concentration (
mg/kg)
IPEN area
1000
100
10
As
Co
Cr
Fe*
La
Mn
Sb
U
Zn*
Elements
Figure 1: Elemental concentrations obtained for C.
texana species collected in sites of different levels of
pollution.
The number of micronuclei increases with the air
pollution, that is, the more DNA molecules split,
the more polluted is the air. For our biomonitoring studies, T. pallida was planted in sixty vases using the same commercial lot of soil and subsequently,
twenty vases were distributed in each chosen sites of
São Paulo city (Congonhas and Cerqueira César) and
Caucaia do Alto, a county located about 50 km from
São Paulo downtown. The collections of adult leaves
were carried out, monthly, for fourteen months.
From the results obtained for T. pallida, analysis
of variance (ANOVA) was applied to verify if they
are significant differences between the mean values
(for p<0.05) obtained for samples collected in three
sampling sites. Statistical test applied to these results
indicated that the samples from Caucaia do Alto presented lower concentrations for the elements Ba, Ce,
Co, Cr, Fe, La, Sb and Sc, when compared with those
from Cerqueira Cesar and Congonhas. By applying
discriminant analysis using SPSS software it was possible to clearly identify three groups of results corresponding to three sites of sample collection. Results
of As, Ba, Ca, Ce, Cr, Fe, La, Mn, Sb and Sc for T.
pallida samples are presented in Fig. 2.
To analyze these plant materials, adequate protocols were established for sampling, sample treatment and analysis using the method of instrumental
neutron activation analysis (INAA). Results obtained
20
Figure 2: Elemental concentrations obtained for T.
pallida species cultivated in three different sites.
1000
Caucaia
ueira Cesar
Concentration ug/g
Cerq
Congonhas
The findings obtained in this study indicate the
possibility of using C. texana and T. pallida species
as an indicator of environmental air pollution.
100
10
1
As Ba Ca Ce Co Cr Fe La Mn Sb Sc
Elements
21
Determination in vitro of inorganic components in human
bone tissues by neutron activation analysis
M. Saiki; M. K. Takata, N. M. Sumita1 , P. H. N. Saldiva1 and C.A Pasqualuci1
1
Escola de Medicina, Universidade de São Paulo.
1486 Bone Meal.
Rib bones were obtained after pathological autopsy of Brazilian people (15 males, 3 females; average age, 54.9 years) at the Institute of Forensic Medicine of the São Paulo University. The samples were
wrapped in polyethylene foils and stored in a freezer
until they were treated for analyses. The ribs were
cleaned free of connected soft tissues (periosteum)
and cut transversely using a saw and then washed
with milliQ-purified water. The trabecular tissues
were separated from cortical ones using a Ti knife
and the cortical tissues were broken in small pieces.
These samples were freez-dried for the analyses. For
total bone analysis, the ribs (cortical plus trabecular
tissues) were calcinated.
Samples and element standards were irradiated at
the IEA-R1 nuclear reactor and the induced gamma
activities were measured using an HGe detector
gamma ray spectrometer. For phosphorus analyses,
the 32 P beta activity was measured using a GeigerMuller detector. Elements Ca and P (at the percentage levels) and Ba, Br, Cl, Fe, K, Mg, Mn, Na, Rb,
Sr and Zn (at µg g−1 levels) were determined in total
rib bone samples and in cortical and trabecular bones.
The statistical t test applied to the obtained results
showed significant difference between the concentrations obtained for cortical and trabecular bones. Ca,
Mg, Na, P, Sr and Zn presented higher concentrations
in cortical tissues than in trabecular ones. For Br, Cl
and K, the highest concentrations were observed in
trabecular tissues. Comparisons made between the
results obtained for Ca, Mg, Na and P for cortical
bones and with the literature values showed a good
agreement.
There has been an increasing interest, in recent
years, in determining trace elements in biological tissues in order to elucidate their roles in human beings as well as to diagnose diseases. Trace element
studies have also been undertaken for bones because
they are deposits of essential and toxic elements and
these determinations can be good indicators for the
detection of different kinds of diseases, such as osteoporosis, age-related chronic diseases and bone cancer.
Further more bones are studied in the investigations
of environmentally and occupationally exposed and
non-exposed populations.
On the other hand, data about trace elements in
bones are very scarce because they present difficulties of obtaining representative specimens for chemical analyses. The bone is commonly divided into
two compartments depending on the hardness, porosity and the content of soft tissue: compact (cortical)
bone and trabecular (spongy and porous, cancellous)
bone, but not all bones can be strictly classified as
compact or trabecular since some types are intermediate in porosity and difficult to classify. Besides in the
case of humans, collecting samples generally presents
problems because of legal-medical implications.
In the present project, human rib bones are being analyzed with two objectives. One of them is
to define adequate experimental conditions to obtain
representative cortical and trabecular tissues for analyzing them separately. The second objective is to
increase the current knowledge of the elemental composition of human bone and for further establishment
of normal values of elements in these two cases separately. Quality control of the results has been evaluated by analyzing NIST 1400 Bone Ash and NIST
22
Inorganic constituents and polymers determinations in
metalized plastic materials from household waste
M. Saiki, E. P. Soares, C. dos Anjos, R. Fulfaro, H. Wiebeck1
1
Departmento de Engenharia Química, Escola Politécnica, São Paulo University
cines. Due to the possibility of toxic compound migration from plastic to the stored material, its use in
such applications is creating a lot of concern regarding the health hazards. In a previous work plastic
samples from packages of foods (soft drink, yogurt,
water, margarine, ice cream) of medical products
(serum, blood, syringe) and cleaning supplies were
analyzed[1]. This report presents results obtained in
the analyses of metalized plastic materials by instrumental neutron activation analysis (INAA) and in the
identification of polymers by the methods of infrared
spectroscopy (IR) and differential scanning calorimetry (DSC). Metallized plastics from food and cosmetic packagings, automobile accessories, toys, house
ware, plastic cards, magnetic cards and compact discs
(CDs) were selected for these analyses. Samples and
the elemental standards were irradiated with a thermal neutron flux in the of IEA-R1 nuclear research
reactor at IPEN and the induced gamma ray activities were measured using a HGe detector gamma ray
spectrometer. Toxic elements such as As, Cd, Cr, Ni,
Sb and Sn as well as Br, Ca, Co, Fe and Zn were determined in these samples. Table 1 shows the ranges
of elemental concentration obtained of these analyses.
Some elements were not detected in all samples.
In the past several decades, the use of plastics has
increased considerably and these days most of it discarded as waste, causing serious environmental problems. Plastic products could contain heavy metals
originated from additives used as polymer stabilizers,
coloring agents, catalysts or filling materials and from
the contamination during the manufacturing or recycling processes. They become serious environmental
problem when the incineration process of the municipal solid waste is used.
Consequently, determinations of toxic elements
and identification of polymers in plastic materials
from house waste are of great interest. From the environmental monitoring point of view, elemental analyses of plastics may contribute to the identification of
possible sources of heavy metals present in municipal
solid waste incinerators and emissions. The identification of polymers is also vital for selecting types of
plastics to be recycled.
At present, the disposal of municipal solid waste
is an increasing problem all over the world and in order to alleviate such problems, the incineration and
recycling processes are being proposed as a feasible
solution to reduce the large quantity of urban solid
waste. Besides, plastics are being extensively used in
storage and packing of foods, drinks, blood and medi-
Table 1: Concentration ranges of elements found in metalized plastic materials.
Element
Toys
As, µg g−1
Br, µg kg−1
Ca, mg g−1
Cd, µg g−1
Co, µg g−1
Cr, µg g−1
Ni, µg g−1
Sb, µg kg−1
Sn, %
Zn, µg g−1
"0"a - 96
298 - 436
"0" - 0.067
"0"
1.7 - 12,4
0.02 - 0.67
"0"
4.4 - 35
"0"
113 - 154
Auto
Accessories
"0" - 0.26
331 - 14819
"0" - 272
"0" - 410
0.017 - 3.7
2 - 25
"0"
5.2 - 5538
"0"
5.1 - 1068
Cosmetic
packaging
0.001 - 0.4
95 - 3039
"0" - 0.68
"0" - 518
0.018 - 8,4
0.08 - 55
"0"
3.8 - 5888
"0"
4 - 593
House wares
Cards
0.017 - 0.8
210 - 2685
0.25 - 1.9
"0" - 27.9
0.04 - 4.5
1.8 - 9.3
"0"
19 - 3898
"0"
37 - 124
0.19 - 0.78
725 - 4381
6.2 - 18.9
"0" - 760
0.15 - 1.4
0.27 - 8.6
"0" - 1115
430 - 21693
0.2 – 7.8
3.5 - 5.5
Compact
disks (CDs)
"0" - 1.3
76 - 452
0.03 - 0.07
"0"
(16-21)10−3
0.17 - 0.45
"0"
3.8 - 155
"0"
5.3 - 5.8
"0" - indicates that the element was not detected in some samples
Results of IR and DSC tests presented in Table
2 indicate that several types of polymers are being
metalized. Results obtained in this work showed that
metalized plastics may contain toxic elements and the
IR and DSC techniques can be used to select plastic
materials for recycling, incineration and also for developing new procedures for recycling.
23
Table 2: Types of polymers identified in metallized plastic materials.
Samples
Methods of identification
IR
DSC
Toys
ABS, PS, BR
PP. ABS, PA 6.6
Auto accessories
PMMA, ABS, PC
PMMA, PE, ABS, PC
Cosmetic packagings
ABS, PP, PS
ABS, PP, PS
House wares
ABS, PA, PP
ABS, PP, PA6.6
Telephone cards
ABS
ABS
Bank cards
EVA, PVC
EVA, PVC
Compact disks ( CDs)
PC
PC
Food packagings
PP, PE, PET, PP,
HDPE, PP, LDPE, , PET, PA 6
ABS = acrylonitrile-butadiene-styrene;
PS = polystyrene;
PA = polyamide;
PMMA = poly(methyl methacrylate);
EVA = ethylene vinyl acetate; PET = poly(ethylene terephthalate)
References
[1] D. H. Nomura, S.F. Mateus, M. Saiki, P. Bode. J.
Radional. Nuc. Chem. 244(2000) 61-65.
24
BR = poly-butadiene;
PC = polycarbonate;
PP = polypropylene;
PE = polyethylene;
Contribution of the neutron activation analysis to evaluate
the mineral absorption by Brachiaria Decumbens in
function of the limestone doses used to recover and
maintain heavily nitrogen-fertilized tropical pastures
M.J.A.Armelin, R.P.R. dos Santos, A.C. Primavesi1 , O. Primavesi1
1
Southeast Cattle Research Center – CPPSE/EMBRAPA, São Carlos, SP, Brazil
Limestone application is one of the less expensive
and effective procedures used to correct soil acidity.
Soil acidity is an important issue in agricultural productivity and in soil management because of the direct effect on development and nutritional constitution of plants, by the decrease or increase of the solubility of some essential nutrients[1]. The acidity correction procedure may occur with limestone distribution on the soil surface, without burying it in, at
pastureland or the so-called direct drill agriculture.
However, it is well known from the literature, that
the pH increase in the soil surface layers may result
in undesirable changes of nutrient and toxic elements
levels in forage tissue. Caires[2], verified that adequate criterions were necessary to estimate the limestone dose to be applied in the Soya culture because a
reduction of Zn and Mn absorption by plant was observed. In case of the intensively managed pastures
with nitrogen, limestone could be one of the key inputs to increase the forage yield and to improve the
quality. Brachiaria decumbens is largely used as forage in the pastures of several Brazilian regions. This
forage is adapted to soils with low fertility and relatively high acidity. According to Valle[3] the pastures of Brachiaria occupy more than 40 million of
hectares in Brazil. The aims of this project are: 1) to
determine both nutrient and toxic element concentrations in the aboveground part of Brachiaria decumbens by Neutron Activation Analysis. Plants are collected in a degraded pasture, submitted to a recovery
process and in intensive management phase, where
different limestone doses were applied to the soil surface after cutting or grazing; 2) to verify the effect
on the absorption of nutrients and other elements by
Brachiaria as a function of the limestone doses applied on the soil surface of this pasture. The field
trial is being performed at the experimental Southeast Embrapa Cattle farm, São Carlos, São Paulo on
the 16 years old Brachiaria decumbens pasture, grown
on a dystrophic Hapludox, being recovered by limestone and fertilizer use. The experimental design was
a randomized block, with 6 replications and 8 treatments. Each block with 100 m2 received a sequence
of limestone doses: 0, 1, 2, 4 and 8 t/ha (T0, T1,
T2, T4 and T8, respectively), besides specific treatments: 2 t/ha of limestone with annual addition of
1 t/ha (T2M), 4 t/ha limestone buried in soil (T4I),
and 4 t/ha of limestone without N fertilizer (T4AS).
The 100 m2 blocks were established in the pasture
and, the main treatments were T0, T1, T2, T4 and
T8, the complementary treatments were: T2M, T4I
and T4S. The forage samples were taken one year after limestone broadcast on soil surface. Instrumental
neutron activation analysis followed by gamma-ray
spectrometry was applied to determine the following
elements: As, Br, Ca, Cl, Co, Cr, Cs, Eu, Fe, K,
La, Mg, Mn, Mo, Na, Rb, Sc, Sm, Th and Zn, in
one of the groups of collected samples (01/22/2002).
Analysis of variance and Tukey’s test (P<0.05) was
applied to the results of elementary concentrations in
the forage dry matter. The following conclusions were
drawn from this statistical analysis: Ca, Mo, Ba, Yb
and Sb were not affected by use of limestone, treatments and blocks. Some elements showed a very high
variation coefficient, a greater number of replications
for more precise results are needed: As, and Cr (between 25 and 30%) besides Ba, Fe, Mo, Sc, Se, Th,
V (between 30 and 40%) and Cs, Na, Sb, Sm (above
40%). As, Co, Cr, Eu, Fe, La, Na, Sc, Th and V
showed variation among blocks. Br, Cl, Co, Cr, Cs,
Eu, Fe, K, La, Mg, Mn, Na, Rb, Sc, Th, V and Zn
were affected by the way of limestone use. Br, Co,
Cr, Mn and Zn showed a negative linear correlation
with limestone doses, while Mg showed a positive linear correlation. These were the first results obtained
for this project that is in progress.
References
[1] J. K. L. Moraes, D. Bellingieri, D. Fornasieri
Filho, J. A. Galon. Sci. Agric., 55/3 (1998) 438.
[2] E. F. Caires, A. F. da Fonseca. Bragantia, 59/2
(2000) 213.
[3] C. B. Valle, J.W. Miles. In: Simpósio sobre
manejo da pastagem, 11, Anais. Piracicaba:
FEALQ, (1994) 191.
25
Application of neutron activation analysis to determine the
essential and toxic elemental concentration in grass forages
cultivated on different soil types and management
M. J. A. Armelin, R. M. Piasentin, O. Primavesi1
1
Southeast Catlle Research Center – CPPSE/EMBRAPA, São Carlos, SP, Brazil
Forages are the main source of food for the ruminant in the tropics. The concept about “nutritious
value” refers to chemical composition and digestibility of these materials[1]. The minerals, which derive
from forages, take part in countless metabolic events
in the animal organism. They perform important role
in the reproduction, in the growth and in the energetic metabolism. In this case, deficiency or excess of
minerals in the plants may reflect in productivity of
the herd, with important economic losses[2]. On the
other hand, productivity of forage results from continuous emission of the leaves and the slender stems
under grazing conditions. The growth process and
nutritious value of the plant are influenced by several
factors such as type and fertility of the soil, physiologic age and species of forage[3]. Instrumental Neutron Activation Analysis (INAA) method was applied
to determine the concentrations of the following elements: As, Ba, Br, Ca, Cl, Co, Cr, Eu, Fe, Hg,
K, La, Mg, Mn, Mo, Na, Nd, Rb, Sc, Se, Sm, Th,
Ti, V, Yb and Zn, which are in the aerial parts of
three tropical forages cultivated in three types of soil.
The sampling, collection and treatment of the sample were carried out by Southeast Cattle Research
Center of EMBRAPA, located in São Carlos, São
Paulo under tropical altitude climate. Forage species
used were: 1) Brachiaria (B. decumbens)cultivated
in Ferralic Arenosol, Orthic Ferrasol, Luvisol without fertilization and Orthic Ferrasol with intense fertilization; 2) Tobiatã ( Panicum maximum) cultived
in Orthic Ferrasol, Rhodic Ferrasol without fertilization, and Orthic Ferrasol with intense fertilization;
3) Batatais ( Paspalum notatum) cultivated in Orthic Ferrasol, Rhodic Ferrasol and Luvisol without
fertilization. The above ground part of the plant,
composed of leaves and slender stem, was considered
in this work. Samples were collected 7 cm above soil
surface. Two samplings were made, in the rainy season and in the dry season. Parts of the samples destined for element determinations, were dried at 60o C
with forced air circulation. The dried materials were
ground in Willey mills and passed through a 20-mesh
sieve (0.84 mm). Aliquots of forage samples weighing
about 200 mg were sealed in clean polyethylene bags
for irradiation in the IEA-R1 reactor. All process of
analysis was carried out in the Laboratory of Activation Analysis of the Research Reactor Center at
IPEN. The analysis of variance and Tukey–test were
used in part of the results, those connected with Ca,
Cl, K, Mg, Mn and Na. The difference (P<0.01)
in the elemental concentration among forages and
among types of soil was detected, except for the K
and Mg contents, and for forage x soil type interaction. Also the difference (P< 0.05) between seasons
of collection was detected, except for Cl content and
in case of Ca, Mg and Na contents, for the forages
x seasons of collection interactions. In general, the
concentrations of Ca and Cl in forages were bigger in
Orthic Ferrasol than in the others. The residual effect of intense fertilization may have caused the high
concentrations of Ca and K presented in Tobiatã cultivated in Orthic Frrasol. In the same way, in the dry
season the Ca, Mg, Mn and Na contents were bigger
and the K contents were smaller. In this case, the
reduction of K contents may have resulted from antagonistic effect among cations caused by increase in
the extraction of Ca.
The analytic method used was sensible enough for
Cl and Na determinations, although the variability
of these minerals had been above 35 %, which also
occurred with Mn. Statistical analysis of the other
results is in progress.
References
[1] L. Gerdes, J.C. Werner, M.T. Colozza, R.A. Possenti, E.A.. Schamman. Rev. Bras. Zootec.,
Viçosa MG, 29(2000)955.
[2] L.R. McDowell, J.H. Conrad, L.G .Ellis, J.K.
Loosli. Bulletin of University of Florida,
ISBN 0-916287-01-7, 1984.
[3] G.O. Mott. In: H.D. Hughes, M.E. Heath, D.S.
Metcalf (Eds.) Forages. Cia. Ed. Continental, p.
131-141, 1966.
26
Determination of mineral and trace elements in brazilian
foodstuffs by using neutron activation analysis.
D. I. T. Fávaro, V. A. Maihara, M. B. A. Vasconcellos, S. M. F. Cozzolino1 , L. K. Yuyama22
1
Departamento de Alimentos e Nutrição Experimental - Faculdade de Ciências Farmacêuticas USP, São Paulo, SP//
1
Coordenação de Pesquisas em Ciências da Saúde /CPCS - INPA, Manaus, Am
In Brazil the present knowledge about the daily
intake of elements and also the content of elements
in foodstuffs is rather poor. The country has approximately 160 million inhabitants from many different
ethnic origins and socio-economical situations quite
different. This diversity has produced many different food habits in various parts of the country[1] and
then the total diets studies become very difficult. The
number of trace elements known to be essential to
humans has increased markedly in recent years. Nutritional deficiency states for some of these elements
have been reported, which have in some cases arisen
from inadequate dietary intakes. Variations in the
trace element content of foodstuffs are now well recognized [2], and demonstrate the importance of direct
chemical analyses of foods and/or diet composites
for the evaluation of trace element intakes. In addition, the existence of trace element interactions in
man[3], emphasizes the importance of a multi-element
approach in the trace element analysis of human diets. Methods of multielemental determination such
as neutron activation analysis (NAA) combined with
high resolution gamma ray-spectrometry applying Ge
detectors and electronic data evaluation are therefore of special interest in the area of toxicology and
nutrition[4, 5, 6] since it is a very accurate and precise technique. Continuing the research in this field, 3
different studies are being developed which has been
carried out at the Radiochemistry Division of IPEN
for several years:
were tested by analyzing the certified reference materials Citrus Leaves (NBS SRM 1572) and Oyster
Tissue (NBS SRM 1566a). This work is being carried
out with the cooperation of Dr Lucia K. Yuyama from
INPA (Instituto de Pesquisas da Amazônia). Also
different diets from this region were analyzed during
this period .
1. Determination of mineral, toxic and trace
elements in foodstuffs and diets from the Amazonic Region by Instrumental Neutron Activation Analysis.
3. Taco Project The group of Food Research
and Studies (Núcleo de Estudos e Pesquisas em
Alimentação-NEPA) from Unicamp, in collaboration with Medicine School of São Paulo (UNIFESP),
Brazilian Society of Food Science and Technology
(SBCTA) and financial support from National Health
Ministry are elaborating a Brazilian Food Composition Table project (TACO project). In the first
step of this project some national laboratories with
good technical capabilities were invited to take part in
the process of choice based on intercomparison runs.
In the first run, held in 1998, the neutron activation analysis laboratory (LAN) of IPEN-CNEN/SP
was considered able to take part in the second step,
since the obtained results by using neutron activation
analysis technique were quite good. In the second
run, during the year 2000, the results obtained were
again quite good and our laboratory was selected to
take part in the elaboration of the Food Composition
Table project. This kind of study is very important
and it is the first one in Latin America.
2. Study of the trace elements and mineral contents of milk and dairy products by
ICP-AES and NAA The mineral and trace element content in food, particularly in milks, is very
important from the standpoint of nutrition and general health. Milk and milk products are a basis source
of some essential elements necessary for the biochemical processes of the human organisms. In the other
hand, due to environmental pollution these products
can contain contaminants, such as Hg, Pb and Cd [9].
This study aims to develop and to improve the analytical methods to analyze the milk and dairy samples.
Different mineralization procedures have been carried
out: a) wet digestion of the sample using concentrated
acid mixtures; b) by dry ashing ; c) by microwave
oven digestions. After this, the ICP-AES method has
been applied to determination of the essential and
toxic elements. Neutron activation analysis also will
be used to determine the essential elements, like Na,
Ca, K, Mg, Mn, Cl, Fe, Zn, Cr, Co, Se.
The Amazonic region is characterized by the availability of fruits rich in pro-vitamin A and fishes with
high proteic content[8]. However, there is little information about the nutritional potentiality of these
foodstuffs mainly concerning the content of fibre, phytate and minerals in the fruits and vegetables. The
purpose of the present work was the establishment
of the chemical composition of these foodstuffs by
using the instrumental neutron activation analysis.
About 25-30 different species of regional fruits and
vegetables (only the edible part of these materials)
were analyzed. Short and long irradiations were implemented depending on the half-life of the induced
radionuclides, and the following elements were determined: Br, Ca, Cl, Co, Cr, Fe, K, Mg, Mn, Na, Rb,
Sb, Sc, Se and Zn by instrumental neutron activation
analysis. The precision and accuracy of the method
27
References
[6] A. Mannan, S. Waheed, J. Radioanal. Nucl.
Chem., Articles, 162(1992)111.
[1] A.A. Figueiredo. Food Reviews International
5(1989)237.
[7] R. Parr. J. Radioanal. Nucl. Chem., Articles,
244(2000)17.
[2] Varo, Int. J. Nut. Res. 1(198)79.
[8] Y. R. Rocha,
R. Shrimpton.
12(1982)787.
[3] H.H. Sandstead, J. Lab. Clin. Med. 98(1981)457.
[4] I. Sheng-Ming, C. Chien, J. Radioanal. Nucl.
Chem., Articles, 161(1992)27.
J.P. Aguiar, H.a
Acta Amazônica,
Marinho,
Manaus,
[9] R.M. Tripathi, R. Raghunath, V.N. Sastry, Kkrishnamoorthy. Scienc. Tot. Environm.,
227(1999)22
[5] A. Mannan, S. Waheed, J. Radioanal. Nucl.
Chem., Articles, 140(1990)91.
28
Nuclear Structure, Reactions and Metrology
The cadmium ratio technique for studying biological
functions of mammalians submitted to uranium ingestion
L. C. Oliveira, C. B. Zamboni, A. C. Cestari1 , G. S. Zahn, M. A. Maschio, A. M. G. Figueiredo
1
Universidade Santo Amaro, UNISA - SP
In the area of health it is usual to perform clinical
examination in blood and urine samples to identify
anomalies in the human organs[1]. These analyses
aim to observe the changes in the concentrations of
Al, Br, Ca, Cl, Fe, Zn, K, Na, Mn, and Mg in these
biological samples. All these conventional analysis
techniques are very expensive and need large samples
of the biological materials ( 2 to 5ml) for each examination. In this study we want to investigate the
physiological alterations on mammalians submitted
to natural uranium ingestion for a long period using
the absolute neutron activation analysis technique.
The Cadmium Ratio technique was used for the
measurement of thermal neutron flux distribution. In
this technique, gold foils, both bare and Cadmium
covered, were irradiated together with the biological sample in the IEA-R1 nuclear reactor at IPEN,
and the γ-ray activities induced in the gold foils by
both the thermal and epithermal neutrons were determined. A HPGe detector in conjunction with ADCAM multichannel analyzer and to a personal computer was used to measure the induced gamma-ray
activity. The concentration of the selected elements
in the samples can be obtained using the absolute
neutron activation analysis technique.
Using this procedure we were be able to determine the following radioactive nuclides: 38 Al (T1/2
= 2.2 min, Eγ = 1779 keV), 82 Br (T1/2 =1.7 d, Eγ
=554 keV), 49 Ca (T1/2 = 8.7 min, Eγ =3084 keV),
38
Cl (T1/2 =37 min, Eγ =1642 keV), 59 Fe (T1/2 =44d,
Eγ =1099 keV), 69 Zn (T1/2 =14h, Eγ = 438 keV),
42
K (T1/2 =12h, Eγ =1525 keV), 24 Na (T1/2 =15h,
Eγ =1368 keV), 27 Mg (T1/2 = 9.5 min, Eγ =844
keV) and 56 Mn (T1/2 =2.6h, Eγ =847 keV). To determine the concentration of these elements in urine
and blood, 100 µl aliquots of each biological sample were pipetted onto 1cm2 pieces of Whatman No
40 filter paper, which were then sealed in individual polyethylene bags. After irradiation, the samples
were also gamma-counted using the same instrumentation, and the concentration of the selected gammaray emitters was obtained by using the expression:
time-related corrections. In this expression values of
thermal as well as epithermal neutron flux and the
respective cross sections at these energies have been
used to determine the element concentration.
To illustrate the analysis procedure, the results involving a blood sample of Beagles will be presented.
The concentration of the elements present in the
blood sample of the dog was calculated and the results are shown in Table 1.
Table 1: Concentration of Al, Ca, Cl, Mg, Mn, Na,
Br and Fe in a dog blood sample.
Element
Al
Ca
Cl
Mg
Mn
Na
Br
Fe
Concentration (µgµl−1 )
0.11 ± 0.03
0.128 ± 0.002
2.24 ± 0.34
0.087 ± 0.013
0.00017 ± 0.00003
1.26 ± 0.19
0.074 ± 0.06
0.29 ± 0.11
The investigation using Beagles is particularly interesting because 90% of their physiological characteristics are similar to the human being[1]. This way
the normal value[2] established for a human being can
be used for comparison. Using this condition, the
urine sample of Beagles was analyzed and the results
were compared to the normal range. These results are
presented in Figure 1. In this case no serious anomalies were observed although a larger chlorine concentration was found for the dog doped with 100ppm of
uranium.
Following advantages could be pointed with the
use of this nuclear methodology to perform clinical
analysis: a) it uses smaller sample quantities compared with the conventional methods for clinical evaluation of small animals. b) it also allows simultaneous determination of several elements in the biological samples, something not always possible in the
conventional clinical analysis procedures. The NAA
can therefore be an alternative method for diagnosing anomalies in biological functions, especially when
sample quantities are limited.
F m(x) = [A(γ)λx M ]/[NA φσmT f ε(γ)I(γ)B(t)] (1)
where: F m(x) represents the concentration of radioactive nuclide (x), A(γ) the measured area of the
selected gamma-ray peak; λx the decay constant, M
the atomic mass, NA the Avogadro number; φ the
neutron flux; σ the cross section for the selected capture reaction mT the mass of the biological sample,
f the isotopic fraction, ε(γ) the efficiency, I(γ) the
intensity and B(t) the parameter that involves all
30
as well as to determine the absolute efficiency of the
gamma detector however, considering that this experiment involved the analysis of hundreds of biological samples, from three experiments with different
mammalians (rats, chickens and dogs), the absolute
method became advantageous, since it is possible to
determine the concentration of elements in each irradiation without the use of standards. The main
disadvantage is that it is necessary to have access to
a nuclear reactor to perform the neutron activation
in the samples.
12
control
20 ppm
100 ppm
upper limit
Cl mg/ml
9
6
lower limit
3
30
60
90
120
150
days
References
Figure 1: Behavior of the element chlorine in the
urine sample of the control and doped dogs.
[1] D. Randall; W. Burggren; K. French; R. Fernald.
Fisiologia Animal Mecanismos e Adaptaes, Ed.
Guanabara (2000).
Another important advantage is in the use of the
absolute method to calculate the concentration of elements in the biological samples using neutron activation. Of course, this procedure is much more demanding, as it is necessary to perform the measurement of the thermal neutron flux for each sample,
[2] J.B. Henry, Diagónsticos Clnicos e Conduta Terapêutica por exames Laboratoriais. 10a ed., Vol.
I (1982).
31
Cosmic ray chronometer
102m
Rh
P. Perso1 , J.Y. Zevallos-Chavez1 , M.T.F. da Cruz1 , C.B. Zamboni, F.A. Genezini, J.A.G. Medeiros, E.B.
Norman2
2
1
Universidade de São Paulo, IFUSP, Brasil,
Lawrence Berkeley National Laboratory Berkeley, U.S.A.
Radioactive isotopes decaying essentially by electron capture (²) , but that have energy available to
undergo β + decay may belong to a category denominated cosmic ray chronometers, depending on their
half lives in laboratory and on their β + decay intensities. The isotopic abundance of these chronometers
in cosmic rays allows us to know details of the isotopic composition at the sources, that is, in supernovae and interstellar dust. They also make possible
calculations of diffusion to treat the propagation of
cosmic rays, testing models for their origin and acceleration mechanisms, coming out with values for their
confinement time in the galactic volume.
The isotope, which in laboratory, has a half life for
electron capture in the range of years and a beta plus
decay intensity small enough, may have its half life increased enormously during the processes of injecting
it in the cosmic rays. It may then propagate through
the interstellar medium for times long enough to allow
its detection in the vicinity of Earth. Above kinetic
energies of 1GeV/nucleon, the processes that inject
nuclei in the cosmic rays let them be totally ionized
most of the propagation time. In such cases, the only
possible decay is β + , purely nuclear, where the phase
space size is usually reduced, together with a typically
high prohibicity (orbital angular momentun carried
by the positron-neutrino system). This increases the
partial half-life (β + , in the interstellar medium will
be the only event) sometimes to about 106 years. We
could then have a cosmic ray chronometer.
The event under study is the 102 Rh decay, whose
characteristics are: a) ground state with t1/2 = 2.9 y,
that decays to 102 Ru and 102 Pd through β + and ε (80
%) and β − (20 %) respectively; b) a meta-stable state
with t1/2 = 207 d, that decays to 102 Ru and 102 Rh
(ground state) through electron capture (100 %) and
isomeric transition (0.23 %) respectively, there are
no known trace intensities of β + or β − decay from
this state. An isomeric transition (of M4 multipolarity) that may represent a ”leakage” form of decay is
extremely converted (theoretical α ∼300) that again
needs the presence of the outer electrons to take place.
The experiment was designed as a γ-ray coincidence spectroscopy to be performed with a system of
four large volume Ge detectors, following the decay of
102m
Rh, in order to determine the intensities of its β +
decay. The level scheme of 102 Rh has changed during
the last years, due to contributions of on- and offline spectroscopy measurements [1] where the correct
ordering and energy spacing between the 207d metastable and the 2.9 y ground-state isomers were determined. The level scheme and decay data presented
in Ref. 1 show that the most probable branch for β +
decay takes place to 1106-keV level in 102 Ru, from energy, spin and parity considerations. The event that
could be a signature of this decay path is the emission
of a positron, followed by a 631-keV γ ray. If annihilation of the positron is achieved close to the source,
observation of the annihilation photons in time coincidence with that of 631 keV is the sought event.
The radioactive source was prepared through the
reaction 102 Ru(p,n)102 Rh, with the 15 MeV proton
beam of the Pelletron Accelerator at the Institute
of Physics, University of São Paulo (IFUSP). After
the irradiation the singles spectra were taken with a
190cm3 HPGe coaxial detector at the Nuclear Structure Laboratory, IPEN to check the presence of the γ
transitions from 102 Rh decay. As the most probable
β + decay of the 102m Rh goes to the 1106 keV excited
state in 102 Ru, that deexcites through a gamma transition of 631keV. The signature we looked as event,
after the due corrections, is a triple coincidence between positron annihilation photons, and the 631 keV
gamma ray (511-511-631 keV triple coincidence). We
performed the measurement with the Multi-Detector
System of Linear Accelerator Laboratory at IFUSP
using four HPGe detectors at suitable geometry for
detecting the annihilation photons together with the
gamma. This coincidence was measured during a total time of 8.4×105 s, producing a total of 1.9×105
events. The time resolution of the coincidence was
16 ns and the efficiency for the events of interest was
5.0×10−3 .
The upper limit set to the β + branch of 102mRh
allows to infer a limit to the partial half-life of that
branch. It is bigger than 1.2×106 years, with a 95
% confidence level. This limit represents a first indicator for 102m Rh to be considered as a cosmic-ray
chronometer.
References
[1] R.B., Firestone, Table of Radioactive Isotopes,
Wyley, (1986).
32
Effects of gamma radiation on the pbs-ks DNA plasmid
K. Shtejer1 , J. D.T. Arruda-Neto2 , C. B. Zamboni, C. L. Duarte, R. Semmler, S. A. C. Jorge3
1
Center of Applied Studies for Nuclear Development, CEADEN, Havana, Cuba
2
Instituto de Física, Universidade de São Paulo
3
Universidade Santo Amaro, São Paulo
plasmid DNA, with 1 MeV gamma radiation. About
10 µl of DNA was irradiated at a concentration of
15ng/µl in a cylindrical plastic tube (eppendorf) in
the 60 Co gamma cell at IPEN facility. The dose rate
was 5 kGy/h. Supercoiled (FI), Circular (FII) and
Linear (FIII) forms of the plasmid were separated by
agarose gel electrophoresis at 10 volts overnight with
1 % agarose.
The results exhibit a decreasing of FI plasmid fraction and an increasing number of the FII and FIII
fractions with the dose, suggesting the presence of
SSBs and DSBs in the irradiated DNA plasmid. The
detectable molecule fractions of each form of plasmid
were analyzed by means of a statistical treatment[4, 5]
allowing the calculation of the average number of SSB
and DSB per plasmid for each interaction dose. In
this analysis it was assumed that the strand break
distribution obeys Poisson’ laws. These calculations
were compared with the corresponding experimental
data. It was found that the statistical results describe
satisfactory the data for gamma radiation.
DNA is considered to be the most important and
critical target in a cell from the point of view of radiation damage. It is responsible for conservation and
transmission of all the cell genetic information. It
is constantly submitted to different kind of damages
and depending on the extent of the damage it could
be repaired. The energy transferred by ionizing radiation to the DNA strands can induce mutation, carcinogenic process and cell death. The DNA damage
involves nucleotide base alterations: single (SSB) and
double (DSB) strand breaks and also chromatin rupture.
The DNA strand break (mainly DSB) is the most
critical damage induced by ionizing radiation. Specifically gamma radiation is used in a large number of illness treatments including cancer diagnosis, treatment
and cure. In fact, this radiation is the base of conventional radiotherapy using 60 Co and 137 Cs sources. Beside, this radiation is also present in treatment which
involves neutrons and others types of particles, such
as protons, alphas and heavy ions (e.g. Ne, Ar).
The 250 MeV proton beam therapy, largely used
in recent years as an effective non-invasive cancer
treatment, produces gamma rays as a secondary radiation, which can generate radiobiological effects on
healthy tissue. This kind of radiation with low linear energy transfer (LET) interacts with the tissue
producing secondary electrons which directly produce
excited and ionized states into the DNA strands inducing the formation of energetic free radicals in the
aqueous solution containing the DNA molecule. The
DNA strand damages produced by these interactions
must be well known in order to prevent the radiobiological effects on human being. The investigation of
DNA radiation effects has been very intensive in the
last years[1, 2, 3] and the present study is a contribution to better understand the mechanism of single
(SSB) and double (DSB) strand breaks of pBs KS (+)
References
[1] A. Chatterjee, Nucl. Instr. Meth. In Phys. Res.A
280(1989)439.
[2] B. Lewin, in Genes V, chapter IV, Oxford Univ.
Press, NY, 1994.
[3] V. E. Cook, R. K. Mortiner, Radiation Research
125(1991)102.
[4] R. Cowan, C. M. Collis, G. W. Grigg, J. Theoretical Biology, 127(1987)2295.
[5] K. Hempel, E. Mildenberger, Int. J. Rad. Biology,
52(1987)125.
33
Neutron flux distribution in an Am-Be neutron irradiator
C. B. Zamboni, G. S. Zahn, K. Shtejer-Diaz1 , T, Madi Filho2 , R. B. de Lima2
1
Center of Applied Studies for Nuclear Development - CEADEN, Havana, Cuba.
2
Nuclear Engineering Center (CEN)-IPEN-CNEN/SP.
A neutron irradiator has been assembled at IPEN
facilities to perform qualitative and quantitative
analysis of many materials using thermal and fast
neutrons outside the reactor premises. To establish
the prototype specifications, the neutron flux distribution was calculated using the Monte Carlo technique. These theoretical predictions then allow one
to discuss the irradiator’s performance. The use of
the neutron irradiator presents the advantage of supplying a stable neutron flux for a long period, thus
eliminating the need for using standard material. The
analysis thus becomes agile, practical and economic.
This prototype consists of an aluminum cylinder
of 5 mm thickness with 1200 mm length and 985 mm
diameter, filled with paraffin, and two perpendicular
cylindrical cavities (B and C), with the same diameter ( ∼80 mm), which cross the prototype’s geometric center. In the metallic cavity B (also of 5-mmthick aluminum) a ruler passes through the longitudinal direction, where the material to be irradiated
can be put in different positions. In the cylindrical
hole (cavity C), the two Am-Be neutron sources are
positioned symmetrically, at the same distance from
the geometric center, face to face.
The Americium-Beryllium sources were obtained
commercially and both have the following specifications: 600 GBq 241 Am-9 Be (α,n) neutron source, with
cylindrical design (40 mm diameter by 70 mm long)
made of corrosion- resistant alloy with neutron emission rate of 3.9 × 107 n/s, each. Two different configurations of the neutron source arrangements, can be
explored:
3,0
En < 0.5eV
0.5eV < En < 0.5MeV
En > 0.5MeV
Total
2,0
5
-2
-1
Neutron Flux ( x10 cm .s )
2,5
1,5
1,0
0,5
0,0
-20
-10
0
10
20
Position (cm)
Figure 1: Neutron Flux Distribution in the Fast Configuration.
5,0
En < 0.5eV
0.5eV < En < 0.5MeV
En > 0.5MeV
Total
-2
-1
Neutron Flux ( x10 cm .s )
4,0
4
3,0
2,0
1,0
0,0
-20
-10
0
10
20
Position (cm)
Figure 2: Neutron Flux Distribution in the Thermal
Configuration.
The results presented in this work provide important information for a better knowledge of neutron
flux distribution in the prototype. According to theoretical simulations, the prototype can be useful to investigate biological, geological, metallic and ceramic
samples. It can also be used to test detectors and to
do quality control check using NAA. However, quantities from mg to g levels of samples are necessary
to achieve good sensitivity, when the material has a
low microscopic neutron cross section, due to the low
neutron flux available.
• Predominantly thermal neutron source: In this
situation a polyethylene cylinder around 50 mm
long is placed between each neutron source and
the sample in order to thermalize the emitted
neutrons.
• Predominantly fast neutron source: In this situation the neutron sources are positioned at 35
mm of the geometrical center.
The MCNP-4C code[1] was used to estimate the
flux for the two different configurations of the neutron
source. The energy ranges considered were: thermal
below the Cadmium cut-off energy (0.5 eV), epithermal (between 0.5 eV and 0.5 MeV) and fast neutrons
(above 0.5 MeV). The results for the predominantly
fast neutron configuration are shown in Fig. 1and for
the predominantly thermal neutron configuration in
Fig. 2.
References
[1] J. F. Briesmeiter (Ed.), MCNP-A General Monte
Carlo N-Particle Transport Code, Version 4C,
LA- 13709 M (2000).
34
Gamma-gamma angular correlation experiments
performed with a multi-detector system
F. A. Genezini, J. Y. Zevallos-Chavez1 , M. T. F. da Cruz1 , C.B. Zamboni, J.A.G. Medeiros
1
Instituto de Física da Universidade de São Paulo
A multi-detector system for coincidence measurements, where there are n detectors, has n(n-1)/2 independent pairs. This representing an important experimental improvement as it reduces the measurement time compared to a two-detector system, one
fixed and the other movable, over the angles ? of
interest. The reduction factor is the number of independent pairs, and we still have to adequately choose
the angles between the detectors, taking into account
the symmetries of the angular correlation function.
The γγ directional correlation function, where no polarization is measured, is a series of even powers of
cos(θ), having a period of π. In addition the function
has a reflection symmetry, about its half-period, π/2.
The other important issue is that differences in the
efficiencies of the various detectors have their effect
on the experimental data in such a manner that the
data points are not joined by a single, smooth, power
series as described above, even after solid angle corrections.
We need to have compatibility among the data to
be fitted, starting from the raw data, which are the
double-coincidence counts obtained with different detector pairs, e.g. ab and cd, indicated by N[ab] (Θ[ab] )
and N[cd] (Θ[cd] ), respectively, where we identify the
angle between the detectors, to prevent ambiguities.
The expression for the angular correlation between
two radiation emitted in a rapid sequence by the nucleus is given by:
X
W (θ) =
Akk Pk (cos θ)
(2)
is a value which depends on the detector pair,
C[ab] =
SY12 a
² (E1 )²b (E2 )
4
(5)
with S being the number of disintegration that occurred during the counting time, Y12 the intensity of
the photon sequence being measured and ² are the
absolute efficiencies of the detectors. The correction
factors Qkk are given by
Qab
kk =
=ak (E1 )=bk (E2 )
, k = 2, 4
=a0 (E1 )=a0 (E2 )
(6)
where
Z
=ak (E1 ) =
dΩ²a (E1 , θ)Pk (cos θ)
(7)
When we add the two independent sets of data
N[ab] (θ) and N[ba] (θ) for the same photons and detectors, the expressions may be generalized, and the
symbol [ab] means that the quantity is symmetric on
the properties of the detectors.
(
)
X
[ab]
N[ab] (θ) = C[ab] 1 +
Akk Qkk Pk (cos θ)
keven=2
(8)
with
C[ab] =
¤
SY12 £ a
² (E1 )²b (Ea ) + ²b (E1 )²a (Ea )
4
(9)
=ak (E1 )=bk (E2 ) + =bk (E1 )=ak (E2 )
=a0 (E1 )=b0 (E2 ) + =a0 (E1 )=b0 (E2 )
(10)
keven ≥0
and
Where, W(θ) is their angular correlation function and
the angle between their directions of emission is θ.
Akk are the angular correlation coefficients, and Pk
(cos θ ) are the Legendre polynomials of order k. Normalization of W(θ) is such that A00 =1 and
dP (θ) = W (θ)
dΩ1 dΩ2
4π 4π
[ab]
Qkk =
where the coefficients are the same as those defined
in Ref. 1, except that now we are including the effect
of the fast electronics on the detection efficiencies.
(3)
is the emission probability of the pair γ1 γ2 within
dΩ1 and dΩ2 respectively, making the angle θ between them. It is known that finite detector and
source sizes produce corrections to equation[1]:
(
)
4
X
ab
N[ab] (θ) = Cab 1 +
Akk Qkk Pk (cos θ)
(4)
References
[1] D. C. Camp and A. L. van Lehn, Nucl. Instrum.
Meth. 76(1969)192.
[2] H. Frauenfelder and R.M. Steffen, Angular distribution of nuclear radiation in K. Siegbahn,. Alpha, Beta and Gamma-Ray Spectroscopy, vol 2,
North-Holland Publ. Co., Amsterdam, (1968).
keven=2
where N[ab] (θ) is the number of coincidences obtained
with detectors whose axes make the angle θ and C[ab]
35
Gamma spectroscopic study of excited levels in
193
Ir
G. S. Zahn, C. B. Zamboni, L. C. Oliveira, F. A. Genezini, M. T. F. da Cruz1 , J. Y. Zevallos-Chavez1
1
Instituto de Fisica da Universidade de São Paulo
The nuclear structure of doubly even nuclei in the
A = 190 mass region have been studied during the
last years. In particular, the discussion involving
the intrinsic equilibrium shape of these nuclei indicates changes from prolate (186,188 Os) to asymmetric
(190,192 Os) and to oblate (192−196 Pt) which affect the
character of the excited states. However, the experimental information about the odd-mass osmium isotopes (Z = 77) remained quite unexplored. As the nucleus 193 Os occupies a central position in the complex
transitional region occurring between the deformed
rare earth nuclei and the spherical nuclei near Lead,
we decided to investigate the excited states of 193 Ir
populated through beta decay of 193 Os (T1/2 = 30,5
h) using a high resolution HPGe spectrometer in an
attempt to better understand its nuclear structure.
The radioactive sources were obtained by the irradiation of 5mg of enriched Osmium (99 % 192 Os)
for a period of 10 minutes in the IEA-R1 reactor at
IPEN, São Paulo, with a thermal neutron flux of 5
x 1012 n.cm−2 .s−1 . The direct gamma-ray spectrum
from about 50keV to 1.3MeV was recorded over more
than 800 hours of live counting. In order to positively identify the origin of the γ-rays, spectra were
accumulated through two successive half-lives. The
precise energy calibration of the γ-transitions spectra was taken with standard sources of 109 Cd, 133 Ba,
137
Cs and 152 Eu. The sources of 133 Ba and 152 Eu
were also used for the relative efficiency calibration
of the detector. Peak areas were evaluated by using
the IDF computer code[1].
The single spectra were taking using a 190cm3
HPGe detector (FWHM=1.89keV at 1.32MeV) and a
ORTEC 671 amplifier in pile-up rejection mode. To
determine the γ-ray energies with a precision similar
to that of primary standards, we used the same procedure described by Medeiros et. al.[2]. The measured
energies were confronted with the data from previous
results[3]. Sixteen γ transitions with energies 61.8,
71.5, 129.5, 153.9, 199.3, 297.3, 299.6, 343.6, 345.4,
395.1, 518.0, 615.9, 661.20, 698.5, 827.9 and 1044
keV were observed for the first time. Besides, two
gamma transitions at 154.7 and 668.4 keV, observed
only in present γ-decay study, were also observed in
193
Ir(n,n’γ)[3] and Coulomb excitation[4] reactions
experiments. Also, the photopeak at 619.2keV pro-
posed in our spectroscopy experiment was reported
in (n, n’γ) nuclear reaction[3].
From the analysis of the energy determinations,
our data revealed no evidence for the doublet at
333.3keV and 337.7keV observed only by Price and
Johns[5], as well as for the photopeaks at 378, 181,
219, 317, 378, 418, 556 and 560 keV, deduced from γγ
coincidences in this same study. The energy at 517
keV, reported solely by Avida et. al.[6], was not observed in our study although the present experiment
has achieved better observation limits. The photopeak at 154.74 keV, previously reported as singlet[5],
is here shown to be doublet at 153.95(7) keV and
155.057(69) keV.
From singles spectra analysis the energies of 74
gamma rays have been determined with a better overall precision than previously, 16 of them at the first
time. In addition, a number of γ-transitions were
confirmed. These new results will give us the opportunity to study the extent to which susceptibility to
deformation affects the low-lying states of this transitional nucleus, in an attempt to better understand
the trends in its nuclear structure.
References
[1] P. Gouffon Manual do programa IDF, Instituto de
Física da Universidade de São Paulo, Laboratório
do Acelerador Linear, São Paulo (1982).
[2] J. A. G. Medeiros, C. B. Zamboni, A. L. Lapolli,
G. Kenchian, M. T. F. da Cruz, Appl. Rad. Isotopes, 54(2001)245.
[3] R. B. Firestone, Table of Isotopes, 8th. ed, Wiley,
N. Y. (1996).
[4] F. K. McGowan, N. R. Johnson, I. Y. Lee,
W. T. Milner, C. Roulet, R. M. Diamond, F.
S. Stephens, M. W. Guidry, Phys. Rev. C,
35(1987)968.
[5] R. H. Price, M. W. Johns,Nucl. Phys. A,
187(1972)641.
[6] R. Avida,J. Burde,A. Molchadzki, Z. Berant,Nucl.
Phys. A, 114(1968)365.
36
Nuclear structure of the low-lying states in the
72
Ge
J. A. G. de Medeiros, C. B. Zamboni, F. A. Genezini, I. M. M. A de Medeiros, S. P. Camargo1
1
Universidade de Santo Amaro, SP, Brasil
Systematic analysis of some of the nuclear properties, like energy, spin and parity of excited levels permits the understanding of the nuclear structure of excited states. The structure of 72 Ge is discussed in terms of nuclear models. Nuclear properties of even-A Ge nuclei (66-78) have been calculated using collective models. Theoretical calculations from vibrational (VM), vibrational-rotational
(VRM), anarmonic-vibrational (VAM) models have
been carried out and compared with experimental results. The excited states in the 72 Ge, calculated from
VM and VRM, is presented in figure1. According to
the calculation, the low excited levels are near the
vibrational limit.
Even nuclei can also be classified roughly according
to the ratio of the excitation energy of the first excited 4+ state to the excitation energy of the first excited 2+ state. This parameter, R = E4+ /E2+ ranges
from a value of 3.33 corresponding to the ideal rotational limit down to the value 2, describing an ideal
quadrupole vibrator. With moderate deformation,
the nucleus can be expected to have both rotational
as well as vibrational degrees of freedom at low excitation energy. The asymmetric-rotor estimate, 2.67
≤ E4+ /E2+ ≤ 3.33 may also be considered. Particularly for even-even Ge isotopes this ration is ∼ 2.2 for
A = 66 and 68. It is near vibrational limit of 2.0 for
A= 70 and 72 and increases rapidly to 2.5 for A= 76
to 78. Theoretical predictions from VAM have also
been compared with experimental nuclear properties
of 72 Ge. In this model besides the vibration a moderate deformation is also considerate. These calculations are presented in Table. The nuclear structure
of the 72Ge and was analyzed using different models and a good agreement was found with the model
which considers vibration degrees of freedom associated with soft deformation.
Table 1: Calculation of the excited states of 72 Ge according to VAM compared with experimental results.
Iπ
0+
2+
4+
6+
8+
10+
12+
Experimental Results
Energy (keV)
0
843
1728
2772
3769
4820
6115
VAM[2]
Energy (keV)
0
834
1728
2682
3696
4770
5904
References
[1] A.S. Davydov,
8(1958)237.
Figure 1: Diagram of the excited states in the 72 Ge
nuclei according to VM and VRM compared with experimental results.
G.F. Filippov,
Nucl. Phys.,
[2] T. K. Das, R. M. Dreizler, Phys. Rev. C,
2(1970)632.
37
Measurements of photoneutron cross-sections for 9Be, 13C e
17
O nuclei using thermal neutron capture gamma rays
R. Semmler, A. W.Carbonari, O. L.Gonçalez1 , L. P. Geraldo2
1
2
Instituto de Estudos Avançados - IEAv/CTA, S.J. Campos, SP, Brasil
Instituto de Pesquisas Cientficas IPECI/UNISANTOS, Santos, SP, Brasil
Photonuclear reaction studies with capture gamma
rays of high-energy resolution (some eV), have been
undertaken at IPEN[1] for some light nuclei using
a limited number (around 14) of excitation energies. Consequently, the experimental data obtained
in these experiments has not been appropriate for the
extraction and interpretation of nuclear parameters
from nuclear models. In order to improve the studies
of photonuclear reactions al low energies, an experimental apparatus, for production and utilization of
up 30 capture gamma-rays lines, with discrete energies until 11 MeV, was installed at a tangential beam
hole of the IEA-R1 research reactor[2]. The main objective of the present work is an experimental study of
(γ,n) reactions for 9 Be, 13 C and 17 O nuclei in the excitation energy interval from threshold to 10,83 MeV
with this experimental set up (figure 1).
Neutrons produced in (γ,n) reactions are detected
by a long-counter system, formed by 48 3 He proportional detectors. In the whole period of this experiment, the long counter efficiency has been monitored
by a calibrated 252 Cf source and the result obtained
was (0,3562 ± 0,0066).
The gamma-ray flux, for the 30 capture targets,
was measured with a coaxial Ge(Li) detector (25 cm3 ,
5 %) positioned along the beam path at 823 cm from
the capture target. A pulser with known frequency,
connected to the Ge(Li) detector pre-amplifier, was
used to correct counting losses due to dead time and
pile up effects. The detector calibration factor, as
a function of the gamma-ray energy, was obtained
by submitting all the detector volume to a standard
gamma beam, produced by a sample of known mass
of nitrogen (melamine). Calibration curves in the energy interval from 3 to 11 MeV, were obtained using
least square fitting and the methodology of covariance
matrix[3]. During all measurements carried through
this experiment, the reactor power was monitored by
a SPND detector installed near the capture target, at
the external wall of the tangential beam tube.
In order to obtain the neutron photoproduction
cross section, as a function of the excitation energy,
it was necessary to develop a methodology to unfold
the set of experimental data Si [4]. The problem consisted in solving a system of N equations with M variables, where N is the number of capture targets and
M the number of gamma lines in the capture gammaray spectra. Two methods of solution were employed:
the iterative method and the least squares method.
The solution of the system of equations by the iterative method consisted in iteratively correcting the
initial set of cross section values at the main gamma
line energies, using an appropriated methodology, in
such way that the n Si evaluated at n-th iteration, for
each case, converged to the experimental value Si .
The process is interrupted when the evaluated result
in an iteration (n Si ) and the experimental value (Si )
differ by a small and previously defined quantity.
The correction criterion adopted in this work
consisted in multiplying the obtained cross section,
in any iteration, by a factor corresponding to the
weighted average of the contribution of all targets
having secondary gamma lines in that energy. In this
iterative process, the random error in the calculated
cross sections appears naturally from the standard
deviation of the weighted average of the relative contributions of all targets in the cross section calculation
at the energy of the corresponding main gamma line.
However, the systematic components of the overall
uncertainty are lost in the iterative method. A computer code (SIGMAP3) was written to perform these
calculations. The solution of the system of equations
by the least squares method is however more realistic
than the iterative method, because it employs a more
rigorous treatment of experimental data involving covariance matrix. A computer program (SIGMALP4)
was developed to realize the matrix calculations according to the least square method formalism[3].
References
[1] M. F. C.Khouri et al., Pub. IEA 251, 1971
[2] R. Semmler, L. P. Geraldo, Nucl. Instrum. Meth.,
A336 (1993)171
[3] L. P. Geraldo, D. L. Smith., Nucl. Instrum, Meth.,
A290 (1990)499
[4] O. L. Gonçalez, L. P. Geraldo, R. Semmler, Nucl.
Sci. Eng., 132(1999) 135
Figure 1: Experimental setup.
38
Electronic equilibrium study in aluminum using CaSO4:Dy
thermo luminescence dosimeter
C. A. Federico1 , L. P. Geraldo2 , O. L. Gonçalvez1 , R. Semmler, A. D. Caldeira1 , L. S. Y. Rigolon1
2
1
Instituto de Estudos Avançados - IEAv/CTA, S.J. Campos, SP, Brasil
Instituto de Pesquisas Científicas IPECI/UNISANTOS, Santos, SP, Brasil
Gamma radiation with energies larger than 1.25
MeV is usually produced in nuclear reactor environments, particle accelerators and in cosmic radiation
fields. For these energies, the response of a dosimeter
varies strongly with the absorber material thickness,
up to a maximum value named as charged particle
equilibrium thickness.
The main goal of this work is the experimental determination of the absorbed dose profile in aluminum
sample irradiated by a collimated quasi monoenergetic gamma beam, in order to obtain a relationship
between the average energy of the gamma radiation
field and the charged particle equilibrium thickness.
Figure 1: TL emission glow curve of CaSO4:Dy with
a Gaussian curve fitted to the main peak.
Quasi monoenergetic gamma beams were produced by a number of thermal neutron capture
targets[1], placed inside a tangential beam port, near
the core of the IEA-R1 (2MW) research reactor.
The absorbed dose was measured by the thermoluminescent emission of CaSO4 : Dy dosimeters[2]
produced at IPEN, placed on various aluminum samples with different thickness. Results of the absorbed
dose profile measurements for an aluminum sample
irradiated by a collimated thermal neutron capture
gamma-ray beam, ranging from 3275 to 7850 keV,
have been reported elsewhere[3]. Some of the results
are briefly presented here.
Figure 2: Absorbed dose profile in the aluminum sample for the gamma ray capture spectrum of the Cr target.
A semi-empirical correction applied to the CSDA
electron range is suggested for fitting the CPTE thickness as a function of the mean energy of the capture gamma-ray spectrum in the interval from 3275
to 7850 keV[3]:
The Charged Particle Transient Equilibrium
(CPTE) thickness[4] was obtained from the analysis of the dose profile for each of the 23 gamma ray
capture spectrum. Figure 2 shows an example of the
dose profile for the gamma spectrum produced by the
Cr capture target. The absorbed dose profile was
obtained by fitting a semi empirical function to the
experimental absorbed dose data[3]. The results for
the CPTE aluminum thickness presented in Table 1
do not fit the Continuous Slowing Down Approximation (CSDA) electron range[5, 6, 7], calculated at the
maximum electron energy produced by the primary
gamma radiation interaction (figure 3).
XCP T E =
RCSDA (E) µ(E)RCSDA (E)
e
ρ
(11)
where is the CPTE aluminum thickness, is the CSDA
electron range at the maximum electron energy produced by the gamma radiation, is the aluminum density and is the photon total attenuation linear coefficient for aluminum
39
References
[1] R. Semmler, L. P. Geraldo, Nucl. Instr. Meth., A
336 (1993) 171-175
[2] L. L. Campos, Appl. Radiat. Isot., 1988, 39: 233236.
[3] C. A. Federico, et al., INAC 2002, Int. Nucl. Atlantic Conf., August 11-16, 2002, Rio de Janeiro,
Brasil
[4] F. H. Attix, Introduction to Radiological
Physics and Radiation Dosimetry. WileyInterscience,1986.
Figure 3: CPTE thickness versus gamma ray spectrum energy. The solid curve is the CSDA electron
range(4,5) and the dashed curve is the proposed semiempirical correction to the CSDA electron range.
[5] M. J. Berger, A PC Package for Calculating Stopping Powers and Ranges os Electrons, Protons
and Helium Ions, IAEA-NDS-144, International
Atomic Energy, Vienna, 1993.
Table 1: T he charged particle transient equilibrium
(CPTE) thickness in Aluminum.
[6] R. Cowan, C. M. Collis, G. W. Grigg, Journal of
Theoretical Biology, 1987, 127: 229-245.
Target
In
Sm
Yb
Na
K
Hf
C
S
Si
Mn
Y
Al
Ti
Be
Se
V
N
Zn
Fe
Cu
Pb
Cr
Ni
Energy (keV)
3275.16
3558.80
3964.84
4082.49 1
4184.01
4247.57
4496.88
4503.77
4682.59
5395.54
5399.82
5433.17
5582.88
5617.03
5869.26
5911.04
5921.91
5983.07
6643.09
6907.32
7337.44
7376.13
7850.02
[7] K. Hempel, E. Mildenberger, International Journal of Radiation Biology, 1987, 52: 125-138.
CPTE (mm)
11.8 ± 3.4
8.04 ± 0.83
8.06 ± 0.46
10.79 ± 0.6
11.4 ± 1.8
10.05 ± 0.68
9.7 ± 2.0
11.5 ± 2.0
13.16 ± 0.49
13.8 ± 1.1
13.56 ± 0.74
13.66 ± 0.49
13.62 ± 0.84
12.4 ± 2.9
12.97 ± 0.75
16.2 ± 1.1
13.32 ± 0.99
14.40 ± 0.58
16.3 ± 1.1
16.5 ± 1.7
17.5 ± 1.5
18.9 ± 1.1
20.0 ± 1.7
40
Standardization of
18
F radioactive solution using a 4πβ − γ
coincidence system
M. F. Koskinas, M. S. Dias
filled with P-10 gas mixture at 0.1 MPa, coupled to
a pair of 3” x 3” NaI(Tl) crystals, was used. Two
energy discrimination windows were selected in the
gamma channel. One of the window selected 511 keV
annihilation quanta, and the other the 1022 keV sumpeak, obtained by simultaneous detection of the two
annihilation photons by the two crystals positioned
over and under the proportional counter. The activities obtained for the two gamma windows selected are
shown in the table 1. These results were corrected by
Auger electron efficiency.
In recent years, the Nuclear Metrology Laboratory
(NML) at the Research Reactor Center of IPEN has
been involved in developing procedures for standardization of radionuclides used in nuclear medicine, in
order to improve the standards produced in Brazil.
One of the selected radionuclides was 18 F, which is
being produced by the Cyclotron of IPEN since 1999.
This radioisotope is used in the biomedical investigation of non-invasive glucose metabolism of brain and
to detect myocardial viability and tumors, by gamma
tomography (SPECT) or (PET).
The disintegration rate of 18 F was determined by
means of a 4πβ − γ coincidence system, using efficiency extrapolation technique and electronic threshold discrimination. The events were registered by a
new method developed at the LMN, which makes use
of a Time to Amplitude Converter (TAC) associated
with a Multichannel Analyzer (MCA).
The 18 F sources were prepared by dispensing
known aliquots of the diluted solution on a 20 µg/cm2
thick Collodion film. These films had been previously coated with a 10 µg/cm2 thick gold layer on
each side, in order to render the films conductive. A
seeding agent (CYASTAT SN) was used for improving the deposit uniformity and the sources were dried
in a warm (45 o C) nitrogen jet. A 4πβ − γ coincidence system, consisting of 4π proportional counter
Table 1: Activities obtained at different gamma-ray
windows.
Gamma-ray window
511 keV
1022 keV
Activity (kBq g−1 )
455.6 ± 2.7
457.1 ± 2.9
As can be seen, the results are in agreement with
each other within the experimental uncertainty. The
slopes in all curves are nearly zero within their experimental uncertainties. This result will be compared
with the one obtained with the National Physics Laboratory (NPL) CRC secondary standard radionuclide
chamber, which is part of an international comparison
sponsored by NPL from UK.
41
Standardization of
186
Re radioactive solution
K. A. Fonseca , M. F. Koskinas, and M. S. Dias
The Nuclear Metrology Laboratory (NML) at the
Research Reactor Center of IPEN has started a program to develop procedures for standardization of radionuclides used in nuclear medicine, in order to improve the standards produced in Brazil. The advantage of rhenium isotopes is its chemical behavior and
low energy gamma rays, which are similar to 99m Tc.
186
Re was produced through the reaction
185
Re(n,γ)186 Re by irradiating natural rhenium oxide sealed in a quartz tube in a thermal neutron
flux of 2x1013 cm−2 s−1 obtained near the core of
the 2 MW research reactor at IPEN. The samples
were irradiated for 30 h and the sample was left to
decay for about 14 days in order to reduce the activity of 188 Re (t1/2 = 17 h) to a minimum level.
The irradiatiated oxide was dissolved in 200 µl of
1M HNO3 and washed with distillated water. The
final volume of solution was 2ml. The sources to
be measured in the 4πβ − γ system were prepared
immediately after the final dissolution by dropping
known aliquots of the solution on a 20 µgcm−2 thick
Collodion film. This film had been previously coated
with a 10 µgcm−2 thick gold layer on both sides,
in order to render the film conductive. A seeding
agent (CYASTAT SN) was used for improving the
deposit uniformity and the sources were dried in a
dessicator. The accurate source mass determination
was performed using a Mettler-5SA balance by the
pycnometre technique[1]. Flame sealed ampoule was
prepared for impurity study and for measurement of
gamma ray emission probability per decay.
The disintegration rate was determined using a
4πβ − γ coincidence system by efficiency extrapolation technique using external absorbers over and
under the sources. The events were registered by a
method developed at the LMN, which makes use of a
Time to Amplitude Converter (TAC) associated with
a Multichannel Analyzer (MCA). The 4πβ − γ coincidence system consisted of a 4π proportional counter
filled with P-10 gas mixture and operated at 0.1 MPa,
coupled to a pair of 3” x 3” NaI(Tl) crystals. The
energy window was set to include gamma-rays from
both β − and EC branches, due to poor resolution of
the NaI(Tl) and low intensity of 122 keV gamma-ray.
The extrapolation curve (figure 1) was obtained by
linear least square fitting using code LINFIT[2] which
incorporates covariance matrix methodology. To obtain this curve the beta efficiency was varied in the
range from 65 % to 89 % using external absorbers.
The main uncertainties involved in the measurement
are: counting statistics, weight, dead time, half-life
and extrapolation curve efficiency. All these uncertainties were included in the fitting. The final activity was obtained with an overall uncertainty of 0.55
%, which is satisfactory for calibrating secondary systems. The method for standardization was the same
used in the standardization of 192 Ir [3], and it shows
that this method can be used for radionuclides which
decay by β − and EC processes, mainly when one of
the branches presents low gamma-ray emission probability as these nuclides. Additional gamma spectrometry measurement was made for determining the
emission probability per decay of 122 and 137 keV
gamma ray of 186 Re.
9.2x106
9.0x106
NβNγ/Nc (Bq g -1)
8.8x106
8.6x106
8.4x106
8.2x106
8.0x106
0.0
0.1
0.2
0.3
0.4
0.5
0.6
(1 - Nc/Nγ)/ Nc/Nγ
Figure 1: Extrapolation curves of Nβ Nγ /NC as a
function of (1- NC / Nγ )/ (NC / Nγ ).
References
[1] P. J. Campion, Procedures for accurately diluting and dispensing radioactive solutions. Bureau
International des Poids et Mesures, Monographie
BIPM - 1, (1975).
[2] M. S. Dias, Internal Report- Linfit-LMN, 1999
(IPEN).
[3] K. A. Fonseca, M. F. Koskinas, M. S. Dias, Appl.
Rad. Isot. 54(2000)141.
42
Coincidence system for standardization of radionuclides
using a 4π plastic scintillator detector
Aída M. Baccarelli1 , Mauro S. Dias , Marina F. Koskinas
1
Departamento de Física da PUC/SP, São Paulo, SP, Brasil
(0.152 ± 0.017) % and for 1.25 MeV (60 Co) it was
(4.90 ± 0.64) %. Activity measurements of 241 Am
and 60 Co were performed and the results showed
good agreement when compared with the conventional coincidence system employing a 4π proportional counter, as shown in Table 1. The following scheduled steps will be the standardization of
electron-capture and positron emitters such as 133 Ba
and 18 F.
A coincidence system using a plastic scintillator
detector in a 4π geometry has been developed and
applied for the standardization of radionuclides[1, 2].
The scintillator shape and dimensions have been optimized for maximum charge particle detection efficiency, while keeping background low and a nearly
constant gamma ray efficiency for different points
from the radioactive source (see Figure 1). The
gamma- ray events were measured with a NaI(Tl)
scintillation counter.
The electronic system for
processing pulses consisted of logic gates and delay
modules feeding a Time to Amplitude Converter with
output to a Multichannel Analyzer.
Table 1: Activity values obtained with conventional
and proposed systems.
Radionuclide
241
Am
241
Am
60
Co
60
Co
System
4πβ(PC)-γ
4πβ(PS)-γ
4πβ(PC)-γ
4πβ(PS)-γ
Activity (kBq/g)
(7.272 ± 0.009)
(7.276 ± 0.012)
(142.72 ± 0.29)
(142.42 ± 0.54)
References
Figure 1: Coincidence system using 4π plastic scintillator coupled to a NaI(Tl) crystal.
[1] Baccarelli, A. M.; Dias, M. S.; Koskinas, M.
F. Coincidence system for standardization of radionuclides using a 4? plastic scintillator detector.
Appl. Radiat. Isot. 58, (2003) 239.
Two radionuclides, namely 241 Am and 60 Co, were
chosen for testing the system.
These radionuclides can be easily standardized by the conventional
4πβ(PC)-γ coincidence system employing a gas flow
proportional counter. The sources were prepared by
depositing quantitative aliquots of radioactive solutions onto a 20 µg/cm2 thick Collodion film, previously coated with 10 µg/cm2 gold layer [3].
The alpha detection efficiency measured with
241
Am was around 95 % and the beta detection efficiency for 60 Co was around 67 %. The beta-gamma
efficiency was measured by wrapping point sources
inside absorbers. The value for 59 keV (241 Am) was
[2] A. M.Baccarelli; M. S. Dias; M. F. Koskinas. Standardization of 241Am by means of coincidence
system using 4? plastic scintillator detector. In: V
Regional Congress On Radiation Protection And
Safety, 29/04 a 04/05, Recife, Brazil (2001).
[3] Campion, P. J. Procedures for accurately diluting and dispensing radioactives solutions. Bureau
International des Poids et Mesures, Monographie
BIPM-1 (1975).
43
Combination of nonlinear function and mixing method for
fitting HPGe efficiency curve in the 59-2754 keV energy
range
M. S. Dias, V. Cardoso1 , V. R. Vanin2 and M. F. Koskinas
1
2
UNIP - Universidade Paulista, São Paulo, SP, Brazil
Laboratório do Acelerador Linear, IFUSP, São Paulo, SP, Brazil
Gamma-ray spectrometry by means of HPGe detectors is widely used for applications due to their excellent energy resolution. In Nuclear Metrology, this
technique has been used for activity determination of
radioactive sources when suitable standards are not
available, as well as for determination of gamma-ray
emission probability per decay[1, 2]. In these cases,
an efficiency curve as a function of the gamma-ray
energy becomes necessary, and the efficiency values
for the desired energies are obtained by interpolation. The present work describes a nonlinear function
in combination with the method of mixing activitycalibrated and uncalibrated gamma-ray sources is applied for fitting the experimental peak efficiency of
HPGe spectrometers in the 59-2754 keV energy range.
The nonlinear function is a combination of polynomial functions in log-log scale defined for three different energy regions. In addition, a step function was
developed for fitting the gamma-ray background under the peak. Further details will be given in a forthcoming publication. A HPGe detector Model EGC-20
Intertechnique with 20.6 cm2 sensitive area, 99.7 cm3
active volume and 20% relative efficiency was used.
The radioactive sources used were IAEA standards of
241
Am, 133 Ba, 152 Eu, 137 Cs and 60 Co. In addition, a
88
Y standard source, calibrated at our laboratory by
means of 4πβ − γ coincidence system, was used. One
24Na uncalibrated source was included in the fitting
procedure in order to apply the Mixing Technique[3]
and extend the energy range up to 2754 keV. The
linear function fitting was a fifth degree polynomial
with mixing resulting in seven parameters. The reduced chi-square was 1.19. The nonlinear function
was a combination of three second degree polynomials giving a reduced chi-square of 1.22, close to the
one obtained with the linear function. Figure 1 shows
the behavior of residues obtained with the nonlinear
function It can be seen that there is no systematic
trend of the points around the fitted line, indicating
no appreciable bias. The ratio between the efficiencies obtained with the calibrated and uncalibrated
curves gives the activity of the uncalibrated source.
The results obtained for the two performed fits were:
2219 (21) Bq and 2215(18) Bq, corresponding to linear and nonlinear fits, respectively. These two values
agree within their uncertainties.
4
Residues (%)
2
0
-2
-4
100
Energy (KeV)
1000
Figure 1: Percent residues between experimental and
fitted efficiencies as a function of the gamma- ray energy. The error bars correspond to the standard deviation in the experimental value (in percent).
A nonlinear fit dividing the 59-2754 keV energy
interval into three regions can give satisfactory results. The accuracy in the interpolation is comparable to the linear fit using a fifth degree polynomial.
Since the nonlinear function is a composition of simple second degree polynomials, it is expected that the
interpolation should be more reliable than a linear
function with several parameters, specially in regions
where there are few experimental points. In these
regions a high degree polynomial may show artificial
oscillations in the efficiency curve.
References
[1] Fonseca K.A., Koskinas M.F. and Dias M.S.
(1998) Measurement of the gamma-ray probability per decay of 126I. Appl. Radiat. Isot. Vol. 49,
No.9-11, 1373.
[2] Simões D., Koskinas M.F. and Dias M.S. (2001)
Measurement of the gamma-ray probability per
decay of 42K. Appl. Radiat. Isot. Vol. 54, 443.
[3] Tramontano R. and Vanin V. R.. (1999) Mixing activity-calibrated and uncalibrated gammaray sources in efficiency calibration. Appl. Radiat.
Isot. Vol. 51, 323.
44
International comparison of
204
Tl radioactive solution
M. S. Dias and M. F. Koskinas
The procedure followed by the Laboratório de
Metrologia Nuclear (LMN) at the IPEN - CNEN/SP,
in São Paulo, for the standardization of 204 Tl is described. This radionuclide has been selected by the
CCEMRI (Comité Consultative pour les Etalons de
Mesures des Rayonnements Ionisants) for an International Comparison due to discrepant results obtained
in a previous comparison held in 1997. The LMN
have participated in this comparison in collaboration
with the Laboratório Nacional de Metrologia das Radiações Ionizantes (LNMRI), from Rio de Janeiro.
Independent results using different techniques were
developed by each of these laboratories and included
in the comparison.
Tl-204 decays 97% by β − emission and 3% by electron capture. This feature makes it in a suitable nuclide to be standardized by the tracing technique[1].
The radionuclide chosen as tracer was 134 Cs , because
of its end-point beta energy, which is similar to that
of 204 Tl. The calibration was performed in a 4πβ − γ
coincidence system selecting a γ−ray window in the
796 keV + 802 keV energy range. In this window the
expected decay scheme correction for 134 Cs is small.
The 204 Tl solution was taken from an ampoule
sent by BIPM. The sources to be measured in the
4πβ − γ system have been prepared by dropping
known aliquots of each radioactive solution on a 20
µg.cm−2 thick COLLODION film. This film had been
previously coated with a 10 µg cm−2 thick gold layer
in order to render the film conductive. Seven mixed
sources were prepared using a 1:2 ratio (β-pure and
β − γ , respectively), in order to obtain similar counting rates for both radionuclides. A seeding agent
(CYASTAT SN) was used for improving the deposit
uniformity and the sources were dried in a warm (45
o
C) nitrogen jet[2]. The source masses were accurately determined by the pycnometer technique[3].
The β − γ tracer has been previously standardized
by measuring several sources prepared by the same
procedure.
The activity was determined by efficiency extrapolation technique using external absorbers over and
under the source. The events were registered by a
method developed at the LMN which makes use of a
Time to Amplitude Converter (TAC) associated with
a Multichannel Analyzer (MCA). When the β − emitter and the β − γ tracer are combined in a single
source, a functional relationship exists between the
detection efficiencies [1]. Applying the extrapolation
technique we can write the expression as:
The function G0 was fitted by weighted least squares
using code LINFIT[4] (Dias, 1999) and the extrapolation to (1 − εβCs )/εβCs = 0 gave the expected N0βT l
value. Suitable corrections for decay were included in
the activities.
Figure 1 shows the extrapolation curve . Experimental points obtained with the present Tl-204 solution were combined with additional points obtained
from the previous Tl-204 International Comparison
(1997) using a normalized function:
µ
¶
Nβ Nγ
1
− N0Cs−134
(13)
Nc
N0T l−204
[Nb Ng / Nc - No(Cs-134)]/No
The value of N0T l−204 was obtained by means of
iterative procedure of minimum Chi-square search.
1,35
1,30
1,25
1,20
Experimental
Fitting
1,15
1,10
1,05
1,00
0,95
0,90
0,0
0,1
0,2
0,3
0,4
0,5
0,6
0,7
(1 - Nc/Ng)/(Nc/Ng)
Figure 1: Results of the International Comparison of
204
Tl.
References
[1] ICRU (1994) Particle Counting in Radioactivity
Measurements, ICRU Report 52.
[2] Wyllie, H.A., Johnson, E.P. and Lowenthal, G.C.
(1970) A procedure for stirring aliquots of radioactive solutions when making thin 4? counting
sources. Int. J. Appl. Radiat. Isot., 21, 497.
[3] Campion, P.J. (1975) Procedures for accurately
diluting and dispensing radioactive solutions. Bureau International de Poids et Mesures, Monographie BIPM - 1.
[4] Dias, M. S. (1998) LINFIT and LOGFIT : Polynomial Least Square Fitting Codes with Covariance
Analysis. Internal report of the Nuclear Metrology
Laboratory, IPEN.
Nβ(T l+Cs) Nγ
− N0Cs = N0T l [1 + G0 (1 − εβCs )/εβCs )]
Nc
(12)
45
Neutron Diffraction
A new neutron powder diffractometer at the Research
Reactor Center, IPEN
C. B. R. Parente, V. L. Mazzocchi, Y. P. Mascarenhas1
1
Instituto de Física de São Carlos, USP, São Carlos, SP, Brasil
A new neutron powder diffractometer is under construction at the 2 MW IEA-R1 research reactor. It is
an upgrading of the old IPEN-CNEN/SP multipur-
pose neutron diffractometer. The main modifications
of the old instrument are presented in Table below.
Table 1:
Modified parts
Detector
Take-off angle (2θM )
Wavelength (λ)
In-pile collimator
Incident-beam collimator
Scattered-beam collimator
Old diffractometer
A single boron trifluoride
(BF3) neutron detector
A Cu flat mosaic
single crystal
36o
1.137 Å
A Soller collimator
A Soller collimator
A Soller collimator
Detector shield
Main neutron shield
A cylindrical shield
A semicylindrical shield.
Beam shutter
A beam port door (a normal
component of the reactor)
Monochromator
Fig. 1 is a photo showing the back of the PSD detector*. Eleven linear PSD proportional counters and
twenty two preamplifiers, two for each counter, form
the detector. The photo in Fig. 2 shows the back of
the Si bent (focusing) monochromator*. At 84o takeoff angle the following reflections/wavelengths(Å) can
be attained: 533/1.111, 511/1.399, 331/1.667 and
311/2.191. The photo in Fig. 3 shows the rotating oscillating collimator* (ROC). The plates were removed
in order to protect them before installation. The
ROC is placed at the entrance to the detector shield
to eliminate parasitic scattering from cryorefrigerator
or furnace heat shield. The photo in Fig. 4 shows the
two main neutron shields, the old and the new, in
the position they will remain for the normal operation of the new diffractometer. Parts constructed in
our laboratory are the main neutron shield, the beam
shutter, the electronic control module for the beam
shutter (see the article in this report), the in-pile collimator, two incident-beam collimators (for different
applications), a mounting and positioning jig (to adjust the ROC in front of the detector shield), the
detector shield and several other gadgets. In comparison to the old instrument, the new diffractometer
will have better resolution and will be ca. 600 times
faster in data acquisition.
New diffractometer
A position sensitive
detector (PSD) (Fig. 1)
A Si bent perfect
single crystal (Fig. 2)
84o
Four different λs
An open collimator
A pyramidal open collimator
A rotating oscillating
collimator (Fig. 3)
A pyramidal shield
A parallepipedal shield + the
old shield (Fig.4)
A shutter formed by two counter-rotating
drums with peripheral square channels
Figure 1:
Figure 2:
47
Figure 4:
The financial support for the project was provided
by Fundação de Amparo à Pesquisa do Estado de
São Paulo (FAPESP), under project no. 95/05173-0,
and Ministério da Ciência e Tecnologia, under project
RXENZCS. Several other people had active participation in different phases of the construction of diffractometer and we thankfully acknowledge their collaboration. The author thank Francisco E. Sprenger,
Edno A. Lenhatti and Alberto de Jesus Fernando for
their help in elaborating detailed projects for different parts of the diffractometer, Cláudio Domienikan,
Fábio de Toledo for their contribution in constructing electrical and electronics parts and Roberto M.
Schoueri for his help in the purchase of the materials
and accompanying the jobs in the machine shop of
IPEN.
*All parts of the PSD system, including the PSD
itself, the Si focusing monochromator and the ROC,
as well as the electronic instrumentation for the system, were manufactured by Instrumentation Associates Inc., 8944 Dexter Gables Ln, Dexter, MI 48130
USA. ([email protected]).
Figure 3:
48
The hexagonal cell parameters of ß-quartz at 1003 k
determined by neutron multiple diffraction
L. C. Campos1 , C. B. R. Parente, V. L. Mazzocchi, O. Helene2
1
1
Universidade de Mogi das Cruzes, Mogi das Cruzes, SP, Brazil
Instituto de Física da Universidade de São Paulo, São Paulo, SP, Brazil
An experimental 00.1 Umweg neutron multiple diffraction (NMD) pattern has been used for the determination of the hexagonal cell parameters of betaquartz, a high-temperature phase of silica (SiO2 )[1].
The pattern was obtained in the IPEN neutron diffractometer, installed at the 2 MW IEA-R1 research
reactor. Sample used was a natural quartz crystal, shaped into a cylinder of size 5 cm diameter x
5 cm height. To attain the beta-phase, the crystal was heated to 1003 K inside a furnace specially
designed for the measurement[2]. Indexing of the
NMD pattern was done by using the computer program INDEXHEX, written by the authors. This program determines the azimuthal angular positions (ϕpositions) where the secondary beams, coupled to the
primary beam, attain their maximum intensities in
a ϕ-scan. In such a ϕ-position a peak is formed in
an Umweg NMD pattern, provided the coupling has
enough strength.
During the first attempts to index the pattern, the
authors realized the ϕ-positions of some peaks were
very sensitive to the variation of parameter a and almost insensitive to the variation of parameter c. Some
other peaks were very sensitive to the variation of c
and slightly sensitive to the variation of a. A very
few of them were equally sensitive to both parameters. Those peaks more sensitive to one parameter
than the other were classified as either good for the
determination of a (gda) or good for the determination of c (gdc)[3]. With such a classification, it became possible to employ an iterative process for the
determination of both a and c with good accuracy. In
the iterative process the value of one of the parameters is used for the determination of the value of the
other parameter which, in turn, can be used to redetermine the value of the former one. The process of
iteration continues till each parameter converges on
a value that does not change within a certain predetermined value. Two methods were employed in the
determinations. In a first method the ϕ-positions of
the experimental peaks, related to an origin in the
pattern, were employed. This method was denominated Absolute Method. To apply such method, the
experimental peaks were first selected according to
their intrinsic qualities, i.e. if they had a regular
shape, were sufficiently isolated from their neighbors
and had a suitable signal-to-noise ratio. The selection resulted in 29 gda and 12 gdc peaks. In a second
method, the azimuthal angular distances between ex-
perimental peaks were used instead of their absolute
φ-positions. This method was denominated Relative
Method. Clearly, in this latter method, each selected
peak used in the first method can be combined with
the other (n-1) selected peaks, provided they belong
to a same category (gda or gdc). However, for a better precision in the results it was preferred to combine peaks with opposite behaviors. That is to say,
for a variation of the parameter being determined,
calculated by INDEXHEX, a peak that has changed
its f-position towards a certain direction in the simulated pattern is combined with another peak that has
moved along the opposite direction. Then, a selection
of pairs of peaks was done taking into account both
behavior and sensitivity of the peaks to the parameter variation. Selection resulted in 71 gda and 36 gdc
pairs good for the determination of a and c, respectively. An iterative process, similar to that used in
the first method, was used in the second method in
order to attain a better accuracy in the results. The
two methods were applied in two different situations,
concerning the uncertainty of the first value found in
the iterative process. In a 1st mode, to determine the
value of the first parameter in the iterative process
the other (fixed) parameter was assumed without an
uncertainty (σ) associated. In a 2nd mode, the fixed
parameter was assumed with an uncertainty associated. It should be stressed that both procedures were
used only for the determination of the first parameter in the first cycle of the iterative process[3]. The
error treatment followed the criteria introduced by
Chechev and Egorov[4]. According to these authors
the mean value of a data set, as well as the uncertainty associated to this value, depends on the value
of chi-square (χ2 ) calculated for the data set. Besides, according to the same authors, the uncertainty
associated to the value of the weighted mean of a
data set must be calculated taking into account the
consistency of the data set. It is noteworthy that,
according to the classification of data sets introduced
by Chechev and Egorov[4], the data sets found for
parameter a were classified as discrepant while, for
parameter c, they were classified as consistent. This
occurred for all data sets found in each cycle of the
two methods, for both modes.
Results of the application of the two methods, both
in the two modes, are listed in the table below. The
number of cycles of iteration in each application is
also listed.
49
Table 1:
Method
Absolute
Absolute
Relative
Relative
Mode
1st
2nd
1st
2nd
Number of cycles
5
12
6
8
a ± σa ()
4.9953 ± 0.0013
4.9957 ± 0.0014
4.99646 ± 0.00058
4.99638 ± 0.00057
c ± σa ()
5.46197 ± 0.00064
5.46184 ± 0.00035
5.46116 ± 0.00044
5.46119 ± 0.00044
[2] V.L. Mazzocchi; C.B.R. Parente, J. Appl. Cryst.
27(1994)475.
Comparing the results of both methods and modes,
listed in table above, one can note the consistency of
the values and that in the Relative Method there was
an improvement in the accuracy of a, the error becoming of the same magnitude as that of c[3].
[3] L.C. Campos. P arâmetros de rede do quartzo-β
a 1003 K determinados por difração múltipla de
nêutrons., Ph.D. Thesis, IPEN-USP (2002).
References
[1] J.D. Dana; E.S. Dana. T he system of mineralogy:
Silica Minerals, Vol. 3. New York: Wiley (1962).
[4] V.P. Chechev; A.G. Egorov, Appl. Rad. Isotopes
52(2000)601.
50
Hyperfine Interactions
Study of magnetic hiperfine fields acting on 140Ce probes in
some rare earth compounds by first principles electronic
structure calculations
J. Mestnik Filho, M. V. Lalić1 , A. W. Carbonari, R. N. Saxena
1
Institute of Nuclear Sciences ’Vinča’, Belgrade, Yugoslavia
Here we pesent an overview of several studies performed with Ce and other rare earth compounds
where the 140 La-140 Ce probes were incorporated in
order to determine the magnetic hiperfine fields
(MHF) acting on 140 Ce nuclei. The aim is to emphasize the importance and limitations of first principles
electronic structure calculations in the interpretation
of the results obtained with perturbed angular correlation spectroscopy (PAC) since besides the aid in
understanding some of the features of the relations
of the hiperfine fields with the electronic behavior in
materials it is also helpful in tracing the properties
of the probes utilized in PAC measurements. The
method employed in these calculations is the Linearized Augmented Plane Waves (LAPW) within the
framework of the Density Functional Theory (DFT)
that is embodied in the WIEN97 and WIEN2k computer codes[1].
25
Tb
Sm
Dy
20
Er Ho
Nd
15
Bhf (T)
Gd
Pr
Tm
10
181
Ta
111
Cd
140
Ce
5
0
-2
-1
0
1
(g-1)J
2
3
4
Figure 1: Partial spin up and spin down DOS for
Ce 4f states in the CeIn3 compound, calculated by
the FP-LAPW method. The dashed line indicates the
Fermi level.
However, some drawbacks with the calculations
have to be pointed out. The Ce magnetic moment
results as a combination of its spin and orbital contributions, being respectively, 0.708 µB and -0.531
µB , resulting in a total magnetic moment of 0.177
µB . Both contributions come mainly from the 4f
electrons. Comparison with the experimental value,
0.65 ± 0.1µB , indicates a bad agreement. This was
attributed to the known fact that the Density Functional Theory (DFT) fails to describe atoms with
highly correlated electrons as in the rare earth atoms
like Ce. There are actually ways to treat these cases
but they were not applied here due to difficulties that
additional external parameters have to be introduced
and then the first- principles philosophy is lost. The
main output of such methods is to split the 4f band
into two bands, one for the occupied part that usually decreases its mean energy and departs from the
Fermi level whereas the other band, representing the
unoccupied part, increases its energy above the Fermi
level. It is expected that this effect would decrease
the width of the occupied part of the Ce 4f band, and
then increase the orbital contribution to both the Ce
magnetic moment and Ce MHF.
The second example is the CeMn2 Ge2 compound.
At low temperatures this compound presents a ferromagnetic component directed along the tetragonal
axis and a helical component in the basal plane. PAC
measurements as a function of temperature indicate
a MHF at 140 Ce having two contributions, one due to
a transferred field from Mn and the other appearing
exclusively from the Ce atoms. The striking feature
in this case is that the measured magnetic moment at
Ce is known to be zero and, at a first sight, one may
expect that the MHF would also be zero.
In the first example, we site the case of CeIn3 compound, where the MHF of 32.9 T at 140 Ce probe and
0.4 - 0.5 T at In, both at 4.2 K were experimentally
determined with PAC[2] and NQR[3] measurements.
Corresponding theoretical values were -25.05 T and
-0.91 T, in good agreement with experiment if one
compare only the magnitude of the fields as their signs
were not determined experimentally.
In addition, important findings not accessible by
the experiment were brought into light: 1) the most
important contribution to the 140 Ce MHF comes from
the orbital field produced by its 4f1 electron (-27.74
T), the contact field is very small (2.2 T) due to
a nearly complete cancellation between the valence
(24.8 T) and core (-22.6 T) electrons and a small
spin dipolar field (0.49 T) arises due to the spin polarization of Ce valence electrons, mainly its 5d shell.
2) The 140 Ce MHF is very small compared with the
MHF of the free Ce+3 ion (192 T) as a consequence of
de-localization of its 4f electron which interact with
the crystalline potential, and not as well shielded as
in the isolated ion configuration. This can be nicely
seen in figure 1 that shows the Ce 4f electronic spectrum as a band. 4) The MHF at In position was also
found from the calculations in good agreement with
the observations, even though the structure is antiferromagnetic and a zero magnetic moment at In site
is expected and observed. The reason is that the In
5p sub-shells are not equally polarized, i.e., its px , py
and pz components are polarized in such a way that
their sum results in zero magnetic moment but not
zero spin dipolar contribution to the MHF[2].
52
pected to be large. It is expected that the electronic
structure calculations will help to understand these
findings. The calculations for these cases are however much more complicated since the probe now is
not a host atom and therefore much more powerful
computer resources are needed to treat them.
After performing the electronic structure calculations, a simple explanation was offered which suggests
that the spin component nearly cancels the orbital
contribution leading to zero magnetic moment but
a net MHF appears since the spin and orbital contributions to the MHF do not cancelc. Again, the
results were not completely satisfactory since the results do not agree completely with experiment. The
calculated spin magnetic moment was -0.70 µB , the
orbital contribution is 0.54 µB and therefore the total
magnetic moment is -0.16 µB . The calculated MHF
was -13.3 T for the contact field, 25.1 T for the orbital, -1.7 T for the dipolar giving a total value fo
11.6 T as compared to the experimental value of 39.0
T. Although one can conclude that the cancellation
of magnetic moment takes place in this case, the result is only qualitative. In addition, surprisingly, it
can be observed that in both examples, (CeIn3 and
CeMn2 Ge2 ), the same composition of the magnetic
moment at Ce is developed. This may again be an
indication of the deficiency of the DFT since it is
known by experiments that the magnetic moment in
these two cases is quite different.
DOS (states/Ry/atom/spin)
400
200
0
-200
0.3
0.4
0.5
0.6
Energy (Ry)
Figure 2: Magnetic hiperfine field at the rare earth
position (R) in RCo2 compounds as a function of 4f
spin, for three indicated PAC probes
References
The third case of interest is the family of RCo2
compounds where R is a rare earth. In figure 2 the
results of the measured MHF is shown as a function
of the 4f spin with several probes substituting for the
rare earth in these compounds. The probes are 111 Cd
(closed d shell), 181 Ta (open d shell) and 140 Ce (open
d and f shells). It can be seen that the measured
MHF presents quite a similar trend, independent of
the probe, suggesting that the different probes feel
more or less the same transferred field from the R
atoms that appears due to the polarization of the d
electrons. What is surprising is the apparent absence
of the orbital contribution to the MHF from the 140 Ce
probes, which according to the examples above, is ex-
[1] P. Blaha, K. Schwarz, and J. Luitz, WIEN97.
A Full Potential Linearized Augmented Plane
Wave Package for Calculating Crystal Properties,
Tech. Univ. Wien, Vienna, 1999, ISBN 3-95010310-4. Updated version of P. Blaha, K. Schwarz,
P.Sorantin, and S. B. Trickey, Comput. Phys.
Commun. 59(1990)399.
[2] M. V. Lalic, J. Mestnik-Filho, A. W. Carbonari,R. N. Saxena, H. Haas, Phys. Rev. B
65(2002)0544051.
[3] Y. Kohori, Y. Inoue, T. Kohara, G. Tomka and P.
C. Riedi, Physica B 259-261(1999)103.
53
Temperature dependence of electric field gradient in
LaCoO3 perovskite using perturbed angular correlation
technique
A.C. Junqueira, R.Dogra1 , A.W.Carbonari, R.N. Saxena, and J.Mestnik-Filho
1
SBS college of Engg. and Tech., Ferozpur- 152001, India
ture range 4.2-1146 K using 111 Cd probe and 4.2-1004
K using 181 Ta probe and in both cases the principal quadrupole interaction was assigned to the probe
nuclei occupying substitutional Co atom sites. Temperature dependence of the hyperfine parameters is
found to be very similar for the two probes in the entire range. Temperature dependence of the quadrupole frequency is shown in figure 1. A second fraction is observed in both cases below 400 K whose
intensity increases considerably at temperatures below ∼100 K. Although the origin of this component
is not well understood at present we rule out the possibility of this being assigned to the probe nuclei substituting La site and believe that this may be due
to the probe nuclei occupying other Co sites, within
the rhombohedral structure. It is possible that the
fraction observed at lower temperature has some relation to the spin state transition of cobalt ions, which
occurs at about 90 K. PAC measurements carried
out up to 4.2 K did not show magnetic interaction
indicating the absence of long-range magnetic order
in LaCoO3 . This is in agreement with the earlier
observations[3, 4].
LaCoO3 has attracted much attention in the past
few decades because of the peculiar way its electronic and magnetic properties change with temperature. One of the important properties of LaCoO3 ,
which attracted the attention of many investigators,
is its unusual temperature dependence of magnetic
susceptibility. The magnetic susceptibility slowly increases with temperature reaching a maximum at
T ≈ 90 K and then shows a Curie-Weiss-law behavior above this temperature[1, 2]. The origin of
the low-temperature increase in the susceptibility is
however not well understood. Neutron diffraction
studies[3, 4] have shown that no long-range magnetic
ordering exist down to 4.2 K, indicating that in the
ground state Co3+ ion has a low-spin nonmagnetic
configuration[5](t62g e0g ). The anomalous behavior of
magnetic susceptibility has been interpreted in terms
of thermally induced spin transition from low-spin
(LS) nonmagnetic state (t62g e0g ) to mostly high-spin
(HS) state (t42g e2g ). The crystal field splitting is almost
equal to the intra-atomic exchange interaction energy
and this causes the spin state transition in LaCoO3 as
a function of temperature. The HS state is reported
to be only 10-80 meV above the LS state. Magnetic
susceptibility measurements below 50 K show that
cobalt ions form localized low spin state and the concentration of thermally excited high-spin Co3+ configurations increases smoothly with temperature[5]. It
is expected therefore that a change in the spin state
of cobalt would result in a corresponding change in
the octahedral Co-O bond length. A detailed study of
LaCoO3 as a function of temperature then becomes
necessary with some suitable microscopic technique
using an appropriate probe at the cobalt ion site.
50
45
LaCoO
3
(
111
Cd)
nQ (MHz)
40
35
30
25
20
15
Extensive PAC measurements were performed in
order to examine, microscopically, the electronic and
structural properties of LaCoO3 perovskite using
111
In → 111 Cd and 181 Hf → 181 Ta probes. The radioactive parent nuclei In and Hf were introduced in
the oxide lattice through chemical process[6] during
sample preparation and they were found to occupy
only Co sites in LaCoO3 . While it is well known that
181
Hf substitutes only the transition metal atom sites
in similar perovskites, the result for 111 In contrasts
with that obtained for LaCr(Fe)O3 perovskites[6]
where this probe was observed to substitute both La
as well as Cr(Fe) sites. The preference for only the
Co site in LaCoO3 has been attributed to a different thermal treatment received by the samples. The
PAC measurements were performed in the tempera-
0
200
400
600
800
1000
1200
Temp (K)
Figure 1: T emperature dependence of the quadrupole frequency
The temperature dependence of EFG did not show
any symmetry related phase change in the region of
550-650 K as has been suggested in some earlier reports. Above ∼77 K the EFG is seen to decrease
almost linearly with temperature. This behavior appears to be consistent with the anomalous thermal
expansion of the crystal lattice observed in the neutron diffraction study and can be explained in terms
of a gradual increase of the Co-O bond distance in
54
LaCoO3 resulting from thermally induced spin transition from the low-spin (t62g e0g ) ground state configuration to high spin (t42g e2g ) state of Co3+ ion.
[3] W.C. Koehler and E.O. Wollan, J.Phys. Chem.
Solids 2(1957)100.
[4] N. Menyuk, K. Dwight, and P.M. Raccah, J.Phys.
Chem. Solids 28(1967)549.
References
[5] M.A. Senaris Rodriguez and J.B. Goodenough, J.
solid State Chem. 116(1995)224.
[1] V.G. Bhide, D.S. Rajoria, G.R. Rao and C.N.R.
Rao, Phys. Rev. B 6(1972)1021.
[6] R. Dogra, A.C. Junqueira, R.N. Saxena, A.W.
Carbonari, J. Mestnik and M. Moralles, Phys.
Rev. B 63(2001)224104.
[2] S. Yamaguchi, Y. Okimoto, and Y. Tokura, Phys.
Rev. B 55(1999)R8666.
55
Applied Physics and Instrumentation
Monte Carlo simulations of x-ray generation and detection
M. Moralles, C. C. Guimarães1 , E. Okuno1
1
Instituto de Física da Universidade de São Paulo
Applications of radiation demand precise knowledge of both, the radiation characteristics and the
amount of energy deposited in the environment.
However, most of the physical systems which are subject to radiation have inherent difficulties to be simulated, due to geometrical complexity and the presence of different materials, like the problems treated
in radiation dosimetry, radiation protection and medical physics. For such simulations the Monte Carlo
method is recommended, and the precision obtained
in the simulations depends much on the computation
time. The employment of Monte Carlo simulations in
the applied nuclear physics techniques has increased
with the data processing capabilities of the commercial personal computers.
One of the available tools to perform Monte Carlo
calculations is the GEANT4 package. GEANT4 is
a freely distributed package, written in C++ language, which provides a set of tools for Monte
Carlo simulations of nuclear and high energy physics
experiments[1, 2].
In this period we have performed studies of generation, filtering and detection of x-rays by using the
GEANT4 toolkit. Two applications were produced:
the first one simulates the x-ray beam produced by a
typical tube, and the second one, the measured x-ray
spectra by a cadmium zinc telluride (CZT) detector.
The simulation results are compared with experimental data.
Experiment: The x-ray beams were produced by
a Philips tube (type MG 450) with a tungsten anode.
The electrons hit the anode at an angle of 22o . Photons cross a 2.2 mm beryllium window before leaving
the tube. The photon beam has a divergence angle of
30o . Different filters can be employed to obtain the
radiation with desired quality. A CZT detector was
used to measure the x-ray spectra for different combinations of electron accelerating potential (kVp) and
filters. The CZT detector (type AMPTEK XR-100TCZT) has a beryllium window with 250 m thickness
, and a Cd0.9 Zn0.1 Te crystal with a volume of 3 x 3 x
2 mm3 . The detector was positioned at the distance
of 6 meters from the x-ray tube. A tungsten collimator, with an aperture of 0.4 mm and thickness of 2.0
mm, was placed in front of the detector window to
maintain the counting rate at convenient levels. The
energy response of the CZT detector was calibrated
with a standard 133 Ba source.
Simulations: The simulation of the performed
measurements have been carried out in two steps. In
the first step, the production of x-ray by the tube
is simulated, and the photon spectrum is recorded
for each kVp value. In the second step, the emission and filtering of a x-ray beam is simulated. The
photon spectrum obtained in the first step is used as
input for the energy distribution of the photons emitted in the second step. The simulations in both steps
employ the low-energy electromagnetic interactions
provided by the GEANT4 toolkit. Electrons interact
with matter via bremsstrahlung and ionization, while
photons, via Rayleigh effect, Compton scattering and
photoelectric effect. The decay of ionized atoms takes
into account fluorescence as the relaxation process of
excited atoms.
The simulation of the x-ray generation comprises
an electron gun, a target and a beryllium filter placed
in a vacuum chamber. Electrons are emitted in a
straight line, directed to the tungsten target surface
within an incidence angle of 22o . Figure 1 shows the
simulated x-ray spectrum for electrons with 180 keV.
Number of photons / electron
0,003
0,002
0,001
0
0
20
40
60
80 100 120
Energy (keV)
140
160
180
Figure 1: X-ray spectrum obtained by simulation with
electrons of 180 keV.
The elements included in the simulation of the xray detection were a photon source, filters, a collimator and a CZT crystal. Filters are disks placed at 21
cm from the source. The detector is placed at 6 m
from the source.
Comparison: Experimental and simulated spectra of the calibration source are presented in Figure
2, with the discrete emissions of 133 Ba. The general
agreement between simulated and measured spectra
is reasonable, but some differences due to effects of incomplete charge collection are observable by comparing the relative intensities of photopeaks. Trapping
of charge carriers in CZT detectors is a well known
effect[3]. Since this effect was not taken into account
in the simulations, some differences between experiment and simulation are expected for spectra with
wide energy range. The inclusion of a model which
57
takes into account the charge collection have been reported in the literature[4], and can be implemented
in our simulation code in the future.
Experimental
Number of photons
0,02
1e-01
Experimental
0,01
0
Simulated
0,02
1e-02
Number of photons
0,01
1e-03
0
1e-04
1e-01
20
40
60
80
100
Energy (keV)
Simulated
Figure 3: Normalised experimental and simulated
spectra obtained with kVp = 100 kV and filtering with
4.0 mm of aluminium.
1e-02
1e-03
1e-04
0
50
100
150
200
250
300
350
References
400
Energy (keV)
[1] Amako,
Katsuya,
Present
Status
of
GEANT4, Nuclear Instruments and Methods in Physics Research, A 453, p 455-460,
2000.
Figure 2: Normalised experimental and simulated
spectra obtained with a 133 Ba source.
[2] Agostinelli, S. et al., Medical applications of
the GEANT4 toolkit, INFN/AE-00/08, SISPubblicazione, Laboratori Nazionale di Frascati,
Italy, 2000.
Normalised spectrum for kVp = 100 keV and aluminum filter is shown in Figure 3. The simulated
spectrum agree very well with the experimental one,
showing small differences of intensity in the 20 - 35
keV energy range.
[3] Redus, B., Efficiency of XR-100T-CZT detectors, AMPTEK Applications Note, ANCZT-1
rev. 1, AMPTEK inc., Bedford, USA, 2000.
These results show that The GEANT4 toolkit is
adequate for simulations of typical systems used in
applications of nuclear physics with low-energy electromagnetic interactions.
[4] Matsumoto, M. et al., Direct measurement
of mamographic x-ray spectra using a
CdZnTe detector, Medical Physics 27, p 14901502, 2000.
58
Small Furnace for Perturbed Angular Correlation
Spectrometer
R. M. Schoueri, C. Domienikan, A. W. Carbonari, R. N. Saxena
A small water-cooled furnace is being constructed
for the measurement of the Perturbed Angular Correlation (PAC) spectrum of the samples at high temperatures (up to 1500o C). The furnace is adapted for the
4-detector PAC spectrometer belonging to the Hyperfine Interaction Laboratory. The furnace temperature
as well as the data acquisition system of the PAC
spectrometer will be controlled through software.
ever (model FE50RP) and has up to 10 ramp/steps
of temperature programming. A Platinum Rhodium
10% - Platinum (type S) thermocouple with ceramic
protection tube will be used for measuring the sample
temperature. Commercially available software supplied by Flycon was installed in a personal microcomputer to control and read the sample temperature.
Another software, which will complement the PAC
data acquisition software (ORTEC Maestro) is being
developed where the preset sample temperature and
its maximum fluctuation limit (T ± ∆T) will determine the enable or disable functions of the PAC data
acquisition system. A block diagram of the temperature control system for the furnace is shown in figure
2. The furnace operation and the data acquisition
system are under test.
The schematic drawing of the new furnace is given
in figure 1. The design is basically an adaptation from
a similar furnace used in the PAC laboratory of the
department of physics at the university of Bonn. The
furnace consists of two concentric aluminum tubes A
and B, each with a wall thickness of 0.5 mm, held
together by an upper and a lower chamber C and D
respectively through a set of neoprene O-rings. The
upper and the lower ends of these chambers terminate in vacuum flange KF-40. The space between the
aluminum tubes serves for the water circulation. The
provision for the water inlet and outlet are provided
in the upper and lower chambers respectively. The assembly of tubes and chambers can be held under vacuum, as the inner tube is isolated from the water circulation system through O-rings. The lower chamber
can be coupled to a 4-way cross flange fitting, fixed at
the center of the spectrometer table, having outlets
for vacuum pump, a dual feed through for thermocouple connection and a dual electrode feed through
for connecting the power supply to the graphite heating element. A semi split tubular graphite furnace is
fixed on top of the electrodes and the thermocouple is
fixed, through a support, inside the furnace. The radiation shield around the graphite heating element is
a refectory alumina tube. The lower parts of the electrodes are water-cooled. The sample to be heated is
sealed in a quartz tube under argon atmosphere and
placed inside the furnace from the top chamber. The
top of the chamber is then covered with a flat glass
plate placed on the O-ring and the system is evacuated to 10−5 mb before heating the furnace.
Figure 1: Schematic drawing of the small furnace for
PAC spectrometer: concentric aluminum tubes (A,
B), upper chamber (C), lower chamber (D), tubular
graphite resistance (E), dual electrode feed through
(F), electrode cooling blocks of copper (G, H), thermocouple (I), TC-feed-through (J), radiation shield (L).
The power supply for the furnace is being constructed locally and will have the capacity of furnishing 60 A at 50 VAC for the graphite heating element.
The micro-processed temperature controller, used for
the furnace, was furnished by a local company Fly-
Figure 2: Block diagram of the power supply and the
temperature controller.
59
A Routing Interface for the Multidetector Angular
Correlation Spectrometer
C. Domienikan, F. A. Genezini, C. B. Zamboni, J. A. G. Medeiros1 , M. T. Freitas da Cruz2
1
Universidade Santo Amaro - UNISA-SP, Brazil
Universidade de São Paulo - IFUSP-SP, Brazil
2
A routing interface has been constructed for the
spectrometer at the Nuclear Structure Laboratory
(LEN), to enable the simultaneous acquisition of up
to 4 gamma-gamma or beta-gamma coincidence spectra at different angles between the detectors. The
spectrometer uses two HPGe detectors, for gammagamma angular correlation measurement, and a set
of plastic-scintillators and a semiconductor detector
for beta-gamma measurements. In this mode of operation the spectrometer generates radiation energy
spectra detected by the slave detector in coincidence
with the energy selected in the master detector, as
a function of angle between the pair of detectors.
However, the spectrometer has a low efficieny because, each experiment needs several very long measurements at different angular positions between the
detectors. Simultaneous acquisition of the several
spectra with detectors fixed at different angles will
increase the efficiency of measurements and optimize
the spectrometer utilization by the laboratory users.
The routing is based on the design of a similar interface installed in the gamma spectrometer of the Hyperfine Interactions laboratory[1]. It works together
with a multichannel analyzer ADCAM (Ortec-919)
that has four analog inputs. These will be utilized
with the spectrometer as shown schematically in figure 1. The new spectrometer will be able to operate
with 2, 3, 4 or 5 detectors resulting in acquisition of
1, 2, 3 or 4 coincidence spectra, respectively. Each
coincidence spectra will corresponds to the detection
of the first radiation by the master detector (A) and
the detection of second radiation in one of the slaves
detectors (B, C, D or E). Each detector will furnish
two output pulses, one corresponding to the radiation energy (e) and the other corresponding to time
of detection (t).
In the master channel, the energy pulse e (slow) is
amplified by a linear amplifier and then fed to a single channel analyzer (SCA-Ortec- 551), which makes
energy selection. The timing pulse t (fast) enters a
constant fraction discriminator (CFD-Ortec-579) and
then a delay unit. The outputs of the SCA and the
delayed-CFD pulses are fed to a coincidence unit.
The valid signal from the coincidence unit (A) is sent
to the routing interface.
The slave channels furnish time pulses (tN ), which
are appropriately delayed and the energy pulses (e).
The routing interface tests the coincidence between
the signals A and tN in a selected time interval and
directs the corresponding energy signal to one of the
four inputs of the multichannel analyzer. The result
is the energy spectra detected by the detector of a
corresponding slave branch in coincidence with the
radiation detected by the master branch. The output signals of the routing interface go to a time to
amplitude converter (Ortec-457) and generates time
spectra between the first radiation γ1 ) and the second
radiation γ2 ) of the cascade, detected by the corresponding master-slave pair of detectors. Preliminary
tests with the random signals, simulating the detected
radiations, verified the correct operation of the routing interface.
Figure 1: Block diagram of the eletronic setup of the
LEN gamma spectrometer (A: master detector; b, c,
d, e: slave detectors; HV: high voltage supply Ortec
659; CFD: constant fraction discriminator Ortec 584;
FFA: fast amplifier Ortec 579; AMP: amplifier Ortec
671; DELAY: delay unit Ortec 427A; TSCA: time
single channel analyzer Ortec 551; AND: coincidence
unit Ortec 414A; MCA: multichannel analyzer Ortec
ADCAM 919; TAC: time to amplitude converter Ortec 457.
References
[1] C. Domienikan, M.Sc. Thesis, IPEN, São Paulo,
2001.
60
Electronic Control Module for a neutron Beam Shutter
C. Domienikan, R. M. Schoueri, C. B. R. Parente
An electronic control module for the beam shutter
of the new neutron diffractometer at the Research
Reactor Center, IPEN has been designed and constructed. The beam shutter is formed by two 500 mm
diameter x 500 mm length counter-rotating drums
with a 92 x 92 mm2 peripheral square channel (See
a schematic of the shutter in Fig. 1). The drums
are filled with barite concrete, for neutron shielding,
and are coupled to each other by a pair of identical
gears. Each drum weighs about 400 kg and is supported by a pair of ball bearings. When the channels
are aligned they are in the right position to allow the
neutron beam, coming from the reactor, to pass and
reach the neutron monochromator. The gear coupling of the drums are arranged such that, moving
one of them in certain direction moves the other in
the opposite direction. Consequently, the channels
go to opposite positions shutting the passage of neutrons. The shutter is driven by a 180 VDC/0.11 A
electric motor, provided with a 100:1 reduction gearbox. A metallic gear attached to the drive shaft of
the motor is coupled to a toothed rubber strap fixed
on the cylindrical surface of one of the drums. They
form a sort of rack and pinion coupling. Movement
and positioning is controlled by the Electronic Control Module below described.
other end of the strap, causes the interruption of the
movement when the channels are exactly in opposite
positions and the green lamp remains lighted indicating beam out. Finally, the black push button is used
to interrupt the movement either to reverse it or to
resume it after a pause.
Other special features of the electronic module are:
1) a third micro switch turns off the power of the circuit in case of failure in one of the micro switches used
for positioning 2) ramps in the voltage applied to the
motor, with a ramp time adjustable between 0 and 10
seconds, allow a soft acceleration and deceleration of
the movement in order to avoid damaging the gears of
the system, particularly in the toothed rubber strap.
A block diagram of the Electronic Control Module is
shown in Fig. 2.
Figure 1: Schematic drawing showing the drums of
the Beam Shutter in two different positions. On the
left (a), the channels are in opposite positions corresponding to the beam out condition. On the right (b),
the channels are aligned corresponding to the beam on
condition.
The frontal panel of the electronic module has
three colored push buttons (r ed, black and green)
that command movement and positioning of the beam
shutter. The system status is indicated by three colored lamps, (r ed, yellow and green), fixed on a panel
board. This panel is placed on the top of the main
neutron shield of the diffractometer for maximum visibility. To align the channels, i.e. to put the shutter in the position beam on, the r ed button must
be pushed. In this the module energizes the motor,
which drives the drums to their right positions. During the movement, both yellow and r ed lamps light
up. To stop the movement in the right position (beam
on) a micro switch placed near the end of the toothed
rubber strap actuates the electronic module to stop
the motor (yellow lamp goes off). With the channels
aligned, only the r ed lamp remains lighted indicating
the beam is on. To obtain the beam out condition,
the green button must be pushed. Similarly to the
former case, green and yellow lamps light up during
the movement. Another micro switch, placed at the
Figure 2: Block diagram of the Electronic Control
Module, designed and constructed for operation of the
beam shutter installed in the new IPEN- CNEN/SP
neutron powder diffractometer.
61
Automatic Control System for Measuring Currents
Produced by Ionization Chambers
F. Brancaccio and M. S. Dias
A data acquisition system for automating the Ionization Chamber measurements was developed at the
Laboratório de Metrologia Nuclear of IPEN, using
a desktop personal computer associated with specially designed hardware and software[1, 2]. The current measurements are based on the rate-of-charge
method[2, 3] where the current is integrated by a
feedback capacitor from an electrometer resulting in
a voltage ramp and the time necessary for this voltage
to change from a known value V1 to V2 is recorded.
The system includes a graphic user interface (GUI)
written for Windows platform. Linearity and intrinsic uncertainty measurements were performed in
order to state the accuracy of activity measurements
performed in this system. System linearity was estimated from 153 Sm decay ionization current measurements. The Linear fitting of experimental data
logarithm results are presented in table 1 and figure 1:
The standard deviation of the residuals is a measure of the system linearity[4].
This value resulted 0.034%, indicating an excellent system linearity. From fitted parameter B (Table 1), the 153 Sm
half-life was determined and resulted (46.329 ± 0.012)
h which is in reasonable agreement with literature,
(46.285 ± 0.004) h, taken from[5]. The intrinsic uncertainty of the system was determined by constant
ionization current measurements with a long halflived radionuclide (137 Cs), for different integration
times. The expected variance from Poisson distribution is proportional to the inverse of integration
time[4, 6]. Therefore, as the integration time approaches infinity, the obtained current deviation will
tends to the intrinsic uncertainty. The results are
presented in table 2 and figure 2.
8
Standard Deviation (%)
7
6
5
4
3
2
1
0
0.0
0.2
0.4
0.6
0.8
t
-0.5
(s
-0.5
1.0
1.2
1.4
1.6
)
Figure 2: Per Cent Standard Deviations of Constant
Current Versus t-0.5.
The solid line in figure 2 corresponds to the linear fitting of experimental data. The extrapolated
value resulted (-0.0185 ± 0.0180)%, indicating that
no significant uncertainty is introduced by the measurement system. Measurements were performed in
order to obtain the Ionization Chamber’s calibration
factors for 18 F and 153 Sm radionuclides. The calibration factors allows the activity determination of a
radionuclide sample, by the comparison of the sample
ionization current to that produced by a well known
Monitor radioactive sample, in order to reduce long
time system drifts. The resulting calibration factors
were (7.978 X 10−8 ± 0.87|V s−1 Bq−1 for 153 Sm.
Figure 1: 153 Sm Decay Current Residuals as a function of time.
Table 1: Fitting parameters obtained in the decay of
153
Sm ionization currenta .
A
B
Parameter
-9.0877 x 10−1
-1.49613 x 10−2
a Reduced
Uncertainty
2.1 x 10−4
4.0 x 10−6
Square-χ: 0.999974
62
Table 2: Per Cent Current Deviations as a Function of t−0.5 .
Measuring Time
t(s)
496.693
131.452
49.274
4.966
1.313
0.492
t−0.5
(s−0.5 )
0.04487
0.08722
0.14246
0.44873
0.87264
1.42595
Standard Deviation
(%)
0.12
0.28
0.57
1.2
3.0
4.2
References
Uncertainty
0.02
0.07
0.16
0.3
0.5
1.5
[4] H. Schrader, Activity Measurements with Ionization Chambers, Bureau International Des Poids
et Mesures Monographie BIPM-4 (1997).
[1] A. W. Carbonari, Research Reactor Center,
CRPq, IPEN. Progress Report (1999/2000).
[2] F. Brancaccio, Automatização de um Sistema de
Medidas de Correntes Produzidas por Câmaras
de Ionização e Aplicação na Calibração do 18 F e
153
Sm, M.Sc. Dissertation, IPEN (2002).
[5] N. E. Bowles, S. A. Woods, D. H. Woods, S. M.
Jerome, M. J. Woods, P. De Lavision,S. Lineham, J Keihtley, I. Poupaki, Appl. Radiat. Isot.
49(1998)1345.
[3] J. P. Guiho, A. Ostrowski, J.P. Simoen, P. Hillion,
M esure des courants faibles au Laboratoire de
Metrologie des Rayonnements Ionizantes, Rapport, CEA-R-4637 (1974).
[6] G. F. Knoll, Radiation detection and measurement, John Wiley & Sons (1989).
63
Development of a dry fission track registration method to
be employed in the uranium determination for several
biological and environmental samples
I. M. Yamazaki, L.P. Geraldo1
1
Instituto de Pesquisas Científicas, IPECI/UNISANTOS, Santos, SP, Brasil
A relatively quick and reproducible method for the
determination of uranium content, at the ppb level,
has been developed for the study of several types
of biological and environmental samples. The technique employed was the fission- track registration in
a polycarbonate plastic sheet, commercially known as
Makrofol-KG, together with an automatic discharge
chamber system for fission- track counting, using aluminized mylar foil as an electrode. Known volume (5
µl) of the standard solutions, in the form of uranyl nitrate, with U concentrations ranging from 1.2 x 10−5
to 5.0 x 10−5 g/l, were deposited on Makrofol-KG
plastic foils, together with 2µl of a 1 % cyastat solution (wetting agent), which reduces the droplet surface tension. During the deposition, the droplet was
carefully spread in such way that a large deposit area
of around 7cm2 were obtained. After evaporation under an infrared lamp, the samples were covered with
an extremely thin layer (20 µg/cm2 ) of collodion (pyroxylin) in order to fix the dried deposits on the plastic foils. A sets of 12 samples piled up together were
simultaneously irradiated, inside an aluminum rabbit
(see Fig. 1), with neutrons in the IEA-R1 reactor,
operating at 2MW.
Figure 2: View of the standard sample deposit of
uranyl nitrate in the Makrofol-KG foil after counting
in the discharge chamber.
The experimental points are the weighted average of 5 independent measurements for each uranium
standard sample. The uncertainties in the experimental results were obtained by considering only the
statistical fluctuations. Three independent measurements for each uranium standard and blank samples
were carried out. Each uranium standard and the
blank sample was counted three times in the discharge
chamber. The best curve fitted to the experimental
data points using the least squares method, was a
straight line. The result is presented in Fig.3
2500
Counts
2000
Figure 1: Aluminum rabbit and piled up plastic foils
with the uranium standard sample deposits.
1500
1000
500
0
After irradiation, the Makrofol-KG foils were
etched in a KOH (35%) solution at 60 o C for 12
minutes and the resulting amplified fission tracks were
counted in an automatic discharge chamber. Figure
2 shows a photograph of the uranium sample deposit
after the counting in the discharge chamber. The resulting calibration curve (number of fission tracks Vs
U concentration) is presented in figure 3.
0
10
20
30
40
50
60
70
mg/l
Figure 3: Calibration curve fission track counting versus uranium concentration.
The method has been applied in our laboratory
64
detection limit (n the ppb range).
to analyze the fertilizer samples. The amount of uranium usually found in fertilizer samples is in the range
covered by the above curve[1]. The lowest detection
limit in this work is around 0,80 µg/l, corresponding to the uranium concentration in the blank sample. This value would correspond to the amount of
uranium in the ppb interval. The dry fission track
method, together with an automatic discharge chamber system for the track counting, presents some advantages when compared to another dry method technique, which employs optical microscope for the track
countings[2, 3, 4]. The measurements performed in
the discharge chamber are quick, total area of the
sample deposit, around 7 cm2 , is counted in a few
seconds and they are very reproducible, around 0,2%
[5]. The inconvenience is in the fact that the discharge
chamber system counting is limited to a maximum
of 1100 tracks/cm2 , due to the track overlap in the
evaporated areas in the aluminized Mylar foil. However, in the case when the optical microscope is used,
the counting area is extremely small and as a consequence, the whole surface of the sample deposit is
not scanned. Therefore, in this situation, it is essential that the deposit is strictly homogeneous, which is
difficult to obtained in practice. Besides, the track fission counting using an optical microscope is tiresome
and time consuming.
References
[1] En, Z., Jumaev, N. and Usmanova, M. M., Radiation Measurements, 25(1995)389.
[2] Qureshi, A. A., Khatak, N. U., Sardar, M., Tufail, M., Akram, M., Iqbal, T. and Khan, H.A.,
Radiation Measurements, 34(2001)355.
[3] Singh, A. K., Kumar, A., Jojo, P. J. and
Prasad, R., J.Radioanalytical Nuclear Chemistry, 238(1998)21.
[4] Singh P., Rana, N. P. S., Azam A., Naqvi, A. H.
and Srivastava, D. S., Radiation Measurements
26(1996)683.
[5] Geraldo, L.P., Cesar, M.F., Mafra, O. Y. and
Tanaka E.M., J. Radionalytical and Nuclear
Chemistry 49(1979)115.
[6] Buchmann, J. H., Sarkis, J.E.S. and Rodrigues,
C., Determination of metals in plant samples by
using a sector field inductively coupled plasma
mass spectrometer, The Science of the Total Environment, vol. 263, p. 221-229, 2000
[7] Vargas, M.J., Tomé, F.V., Sánchez, A. M.,
Vázquez, M.T.C. and Murillo, J.L.G., Applied
Radiation Isotopes 48(1997)1137.
The dry fission track registration method which
is employed for the study of biological and environmental samples, is an alternative method for uranium analysis in addition to the other usually employed techniques such as: mass spectrometry[6],
alfa spectrometry[7], fluorimetry[8], neutron activation analysis[2], UV-vis with Arsenazo III
spectrophotometry[9], X-rays fluorescence[10] among
others. The main advantages of the present dry
method technique are: low operational costs if a nuclear reactor is available for the sample irradiations,
simplicity of all instrumentation used and the lower
[8] Ramdoss, K., Amma, B.G., Umashankar, V. and
Rangaswamy, R., Talanta 44(1997)1095.
[9] Rohwer, H., Rheeder, N. and Hosten, E., Analytica Chimica Acta 341(1997)263.
[10] Carvalho, M.S., Domingues, M.L.F., Mantovano, J.L. and Filho, E.Q.S., Spectrochimica
Acta B 53(1998)1945.
65
Neutron Radiography at CRPq
R. Pugliesi, M. O. de Menezes, M. A. S. Pereira, M. L. G. Andrade
Neutron Radiography(NR) is an imaging technique which provides images similar to X-ray radiography. The difference between neutron and X-ray
interaction mechanisms produce significantly different and often complementary information. While Xray attenuation is directly dependent on atomic number, neutrons are efficiently attenuated by some specific elements. For example, organic materials or water are clearly visible in neutron radiographs because
of their high hydrogen content, while many structural materials such as aluminum or steel are nearly
transparent[1].
The NR activities in IPEN are being carried out
since 1988 and the radiographs are obtained either
by using conventional X-ray films or polymers. More
recently, we have also developed and employed a realtime system. The radiography equipment is installed
at the beam line 08 of the pool type 2MW, IEAR1and provides a neutron flux of 106 n/s.cm2 at the
irradiation position[2].
Figure 1: Radiograph of an artificial heart prototype.
1) NR with conventional X-ray films In this
method, the image is formed in conventional X-ray
films, by using a gadolinium converter screen. The
high contrast obtained in the image provides a high
sensitivity to discern changes in material thickness,
and this is one of its main attractive features for NR
purposes. The neutron radiography group of CRPq
has developed such a method and presently it is available for non-destructive testing. The radiography is
obtained in about 5 minutes. The spatial resolution
achieved in the image is about 100 µm and the sensitivity to discern thickness of iron is about 40 µm[3]
The figure 1 shows a typical example of a radiography
obtained by using the film Kodak-AA.
Figure 2: Radiography of a spray vessel.
2) NR with polymers In this method, the image
is formed in polymers by using a boron based converter screen. The insensitivity of the polymers to
visible light, β and γ radiations and the high spatial
resolution achieved in the image, are some of the characteristics that make the polymers attractive for NR
purposes, specially to inspect highly radioactive samples. The neutron radiography group has completely
developed this method and it is currently available
for non-destructive testing. The time interval necessary to obtain a radiography is about 2 hours and
the values for the spatial resolution and sensitivity
to discern thickness of materials are 15 µm and 350
µm(for iron) respectively[4]. The figure 2 shows a
typical example of a radiography obtained by using
the polymer CR-39.
3) Real-time neutron radiography Real-time neutron radiography consists of the continuous visualization of an image using a scintillator converter screen
and a video camera. The direct examination of dynamic events under neutrons can be observed. The
resulting information helps in understanding the dynamic behavior of complex systems. The improvement of video equipment, cameras and computers
has contributed to a growing development program
and application of this technique. This radiography
method is available at CRPq by making use of a
highly sensitivity digital video camera along with a
high performance computer. The figure 3 shows a
typical example of a real-time image obtained (5).
66
References
[1] H. Berger. N eutron Radiography - A state of
art report., NTIAC-SR-98-01. NASA (Center for
Aerospace Information): Aug, 1998.
[2] M. P. M. Assunção, R.Pugliesi, M.O.de Menezes.
Int. J. Applied Radiation Instrumentation
45(1994)851.
[3] R. .Pugliesi; M.O.de Menezes; M.L.G.Andrade;
M.A.S.Pereira; M.S.J.Maizatto. I nspection of
an Artificial Heart by the Neutron Radiography Technique. 3rd International Topical Meeting on Neutron Radiography Luzern Switzerland
March 1998. Nuclear Instruments and Methods in
Physics Research A 424(1999)248.
Figure 3: Real-time neutron radiography image of water movement inside a metallic cavity.
[4] R. Pugliesi; M. A.S Pereira. Nuclear Instruments and Methods in Physics Resaerch(A),
484(2002)613.
4) New developments Recently the neutron radiography group is developing a new radiography methodology which makes use of low-energy radiation beams
to inspect low- thickness materials, of the order of
µm. This methodology will be very useful to inspect,
for example, biological and medical samples as well
as documents.
[5] M. O. Menezes; R. Pugliesi. Real time neutron radiography at the IEA- R1m nuclear research reactor. XXV Reunião de Trabalhos da Física Nuclear
no Brazil. São Pedro 09/2002.
67
Reactor Operation
IEA-R1 Research Reactor Operation and Maintenance
R. Frajndlich
In the biennium 2001/2002 the IEA-R1 research
reactor operated most of the time at a power of 2
MW and the operation schedule of 40 to 64 hours
per week. The operation and maintenance area of
the reactor is composed of three groups as follows:
the operation group, the maintenance group and the
technical support group. The operational group has
a crew of 18 licensed operators and 4 operators under
training, responsible for the reactor operation, routine of sample irradiation in several reactor core positions, tests, experiments and control of operational
documents. The maintenance group consists of 10
technicians for the preventive and corrective reactor
systems maintenance, study of ageing and maintenance records. Technical support group, consisting
of two people, is dedicated to neutronics and termohidraulics calculations. As in the previous years, several changes in the reactor systems were made under
a continuous reactor modernization program, which
aims at increasing the reactor power from 2 to 5 MW
and increasing the operation cycle initially to 64 hours
continuous per week and then gradually to 120 hours
continuous per week. The reactor modernization program was started a few years ago to prepare the reactor for the production of 99 Mo by (n,γ) reaction and
99
Tc generator using gel process. IPEN is the exclusive supplier of 99 Mo(99 Tc) generator kits to more
than 260 hospitals and medical clinics in the country.
Presently all of the 99 Mo is imported from MDS Nordion and the 99 Mo(99 Tc) generator kits are produced
at IPEN for distribution. It is intended to substitute
10-20% of the imported 99 Mo by local production.
The power upgrade and extended operation of the
reactor will also permit the production of 131 I fulfilling the entire demand of this isotope in the country with additional saving in the foreign exchange.
Among the major modernization projects which were
realized are: Substitution of 10 existing graphite reflector elements with beryllium and the installation
of 3 beryllium irradiation devices in the reactor core,
introduction of four isolation valves in the pneumatic
irradiation system to avoid pool emptying, preventive
maintenance of two primary and two secondary water pumps of the reactor cooling systems, renovation
of the water cooling tower of the secondary system
and construction of a high activity sample transfer
system after irradiation in the reactor core. Once
in a month, the reactor operation and maintenance
group prepares a technical report[1] containing information on the monthly activities of the reactor.
The report contains information such as the number of reactor operation schedule, energy dissipated
in this period, reactor core configurations, chemical
and physical characteristics of the water systems, radioisotopes concentration in the pool water, number
of reactor shutdowns, number of irradiated samples
in the reactor core and pneumatic rabbit system and
the radioprotection data. The main operational parameters of the biennium 2001/2002 are:
• Reactor power: 2MW
• Reactor operation time: 3.531 hours
• Energy dissipation: 7.114 MWh
• Reactor operation at low power: 33
• Samples irradiated in the reactor core: 1808
• Samples irradiated from rabbit stations: 1172
• Number of new core configurations: 1
In 2001 the Research Reactor Center (CRPq)
started the necessary documentation and training
of the personnel for the implementation of a quality management systems (QMS) in compliance with
NBR ISO 9001 version 2000. With hard work and cooperation from every member of the reactor staff we
obtained the certification of ISO 9001:2000 for the
“Operation and Maintenance of the IEA-R1 Reactor
and Irradiation Services” granted by Fundação Carlos
Alberto Vanzolini on December 13, 2002.
References
[1] S.P. de Souza, Relatório mensal de atividades do
reator IEA-R1, 2001/2002.
69
A remote radiation level monitoring system for the IEA-R1
reactor building in the case of a radiological emergency
J. P. N. Cárdenas and Chr. R. Romero
types of monitoring system modules are: The 131 I activity monitor in the pool room is a NaI(Tl) detector
system (Victoreen – 840-2) calibrated for the 131 I energy. The Noble Gases Monitor is placed in the pool
hall for gaseous activity measurement in MBq/m3 like
Kr, Xe, Ar, Rd, etc - OTC-421 equipment from Overhoff Technology Corporation.
Data acquisition board and software
The remote output signals (in volts) of each radiation modules (area, duct and gas) are connected to
an analog data acquisition board (AT-MIO-16E from
National Instruments) located in a personal computer. This board is responsible for the data acquisition and signals processing using a specific program
based on Visual Basic Software[1].
Instituto de Pesquisas Energéticas e Nucleares IPEN has 5 important nuclear or radioactive installations and in the case of an accident in any one
of them, the Institute has a Radiological Emergency
Plan. The plan is designed to coordinate all procedures to secure safe conditions for workers in these installations, for general population living in the neighborhood and the environment. One of major nuclear
installation at IPEN is the IEA-R1 research reactor.
It is an open swimming pool type reactor operating
since 1957. The reactor presently operates at 2MW
power level with an operational schedule of 64 hours
continuous a week. The reactor has a specific Radiological Emergency Plan of its own that establishes
procedures and rules for its workers and for other people, living at the exclusion area, in the case of an
emergency situation. Among these procedures, there
is one, which requires that the installation has technical conditions to obtain precise information regarding
radiation levels of the affected areas in the case of an
emergency situation. In order to measure the radiation level at different points in side the reactor building without unnecessary exposure risk to workers, we
have developed an instrumentation designed for radiation monitoring. This will allow a remote surveillance of radiation levels, registering radiation doses as
well as activities of some specific radioisotopes inside
the reactor containment building. We describe here a
data acquisition system for a remote radiation monitoring of the IEA-R1 reactor containment building.
The results of this continuous monitoring are used as
a means of support in a radiological emergency situation. The radiation level data are shown by means
of a computer graphics screen developed for Windows
environment using Visual Basic software[1]. In the reactor building, radiation monitoring is carried out by
means of area and duct radiation monitors installed
at different places as follow:
Figure 1: Data acquisition system block diagram.
8 channels of the acquisition board use signals
ranging from 0 to 5 volts coming from the corresponding circuit modules (signals conditioning) in the Data
Acquisition System (SAD) rack (see Figure 1)[2]:
Software for the data acquisition and processing
was developed to achieve the following objectives: a)
Acquisition of parameters in real time b) Capacity
to generate files about operation course c) Management of the following operations: - data acquisition
and storage (NI DAQ Board) - update screens periodically - print the information - build a process data
base
The following illustrations (Figure 2 figure 3) and
show two of the screens generated in real time, (simulation) of IEA-R1 reactor operation for the Radiation
Emergency Plan Figures 2 and 3).
MA1, MA2 - reactor core support bridge MA3north face in the pool hall MA4 - near Beam Hole
#8 – first floor MA5- experimental hall – first floor
MA6- south face of pool – first floor MA7- machine
room MA8- east face of pool – first floor MA9- water
treatment system – machine room MD1- air exhaust
system of experimental hall – First Floor MD2- air
exhaust system pool hall MD3- general air exhaust
system MD4- gas outlet in the chimney Noble gas
monitor- in the pool hall 131 I monitor- in the pool
hall
Area monitors consist of a detector system
(Victoreen-model 897A-210+ 956A-201). The duct
monitor is a NaI(Tl) detector system (models 94335 + 942A-200) also from Victoreen. The other two
70
Figure 3: Report screen and MDB table(Access).
The radiation monitoring instrumentation installed in the reactor (detectors, processing modules
and displays) meets the necessary requirements for
data acquisition but will require periodic calibration
plan (each 2 years) in order to maintain the system
reliability. The computational system works well, allowing the automation of the reactor building radiation parameters and eliminating the necessity of radiation monitoring through health physics technicians
in the case of a serious radiological emergency. The
data acquisition system shows parameters related to
radiation environment, such as activity, dose and concentration in real time and displays a periodic data
bank (*.MDB files) allowing the surveillance of the
operation records anytime, leading to studies and
analysis of radiation levels.
Figure 2: Digital Monitoring screen.
References
[1] J.P.N. Cárdenas - Continuous thermal balance
monitoring for IEA-R1 nuclear research reactor
power determination, M.Sc. Thesis – IPEN 2000
[2] Hiromoto Y. e Tanomaru N. Instalation and Operation Manual of SAD IEA-R1. CTMSP, Novembro, 1995
71
Vibration Monitoring of the Primary Cooling Circuit
Pumps of IEA-R1 Research Reactor
Érion de Lima Benevemuti and Daniel K.S.Ting1
1
Centro de Engenharia Nuclear, IPEN-CNEN/SP
For approximately 2 years, we have been studying
a reliable form of monitoring the vibration in the primary cooling circuit pumps of the IEA-R1 research
reactor at IPEN. Due to technical and economic features, vibration analysis has been carried out exclusively through a portable data aquisition and analysis
system, using LabView and Matlab softwares. All
sensors are a group of fixed accelerometers. The
analysis tools were established by the nature of sought
defects and they are in similar to what is more commonly employed in this field: RMS speed from 10Hz
to 1 kHz, speed spectrum up to 500Hz, acceleration
spectrum up to 10kHz and envelope spectrum for high
frequency bands. The sought defects are the most
frequent for this kind of monitored equipment : misalignment, imbalance, looseness and rolling element
bearing problems. Routine surveillance of pump vibration, plus the reading of all material found in the
literature, served as a base for accomplishing the best
application procedures for the referred tools. As part
of this work, we carried out a study to determine
the best filtering bands to be used in the envelope
technique for the rolling defects vibration monitoring. The main results obtained up to now can be
summarized as follows:
Defect identification modes:
(DOR) for one of the inertial steering wheel rolling
element bearings. The pump was repaired in July
of 2001 and when the rolling element bearing was
opened an accentuated sapling of its outer race was
verified.
• Looseness in rotating parts may cause an increase in the first rotation harmonic, as well as
in some inter-harmonics.
• Misalignment can increase the second and
fourth rotation harmonics and, if accentuated,
it may also increase RMS speed between 10Hz
and 1kHz.
• Imbalance caused an increase in the first rotation harmonic.
2) Alert limits:
• Comparison of signal historical behavior with
the equipment occurrences knowledge made
possible the establishment of several transition
limits between an acceptable vibration and a
defect vibration. It can be mentioned the value
of 1,4 mm/s for the first rotation harmonic in
the motor bearing as an indicative of an imbalance development.
• Lubrication problems in the rolling element
bearings produced a general and random increase in vibration between 1kHz and 10kHz
and a big and random variation in the characteristic frequency widths.
3) More frequent defects:
• We can verify that the most frequent defects in
the monitored equipment were rolling problems
and looseness in its rotative parts. This kind of
observation gives us clue about the future problems and what should be monitored.
• Defects in the rolling components, besides
increasing the vibration between 1kHz and
10kHz, they also increased the characteristic
frequencies, not only in the envelope spectrum,
but also in simple speed spectrum.
Our experimental observations confirmed, in
agreement with the available literature, that the chosen tools are adequate monitoring primary circuit
pumps of the research reactor IEA-R1 at IPEN.
As an example, we can verify in the graph below,
a large decrease in the outer race defect frequency
72
Corrective maintainance of the primary cooling circuit
pumps of the IEA-R1 research reactor
A.V. Leite, E. L. Benevenutti, G.F. Maciel, M. O.Martins, M. Yovanovich, M.R. Carvalho, E.N.B. Santos
The primary cooling circuit consists of the swimming pool with nuclear core, convection valve, radioactive (16 N) decay tank and two heat exchange
circuits. Each heat exchange circuit contains a centrifugal pump for water circulation, a heat exchanger,
pipelines, valves and control instrumentation. The
coolant water circulation pumps have identical characteristics and possess flywheels to maintain cooling
for sufficient period of time to reduce the decay heat.
In order to guaranty the correct functioning of the water circulation pumps, the reactor is equipped with a
Rotary Equipment Monitoring System (REMS), basically consisting of vibration and temperature sensors,
which monitor the operational conditions of these
equipments in real time. The primary cooling circuit pumps go through periodic corrective maintenance. We will briefly describe the corrective maintenance procedure followed in the case of primary circuit pumps. The maintenance work is described in
two sections, one for each pump.
Maintenance of Pump CP-BOM-01
The pump was dismounted because it presented
variation in the normal level of noise, detected by
RESM, and raised suspicion about potential mechanical problems. During demounting of the pump and
motor system it was verified that some of the components required substitution and others needed repair:
which needed substitution, there were visible cracks
in the impeller throughout its extension. The manufacturer of the pump was contacted for the purchase
of a new impeller. Due to the obsolescence of the component the manufacturer supplied a standard impeller
without four holes for hydraulic balance and a diameter, which was bigger than the original piece. The
manufacturer was requested to machine the impeller
to a diameter which would be close to the nominal
pumping power of the original equipment and at the
same time will be in conformity with the values of
flow and pressure given in the Safety Analysis Report of the reactor. The manufacturer agreed to machine the impeller and drill the holes for hydraulic
balance. During reassembly of the motor and pump
system it was found necessary to re-machine the inner casing of the pump to correctly accommodate the
impeller. All the gaskets and couplings, the bearings
in the stuff box and two bearings of flywheel were replaced with new ones. The assembly was tested at its
normal working regime by measuring the motor current. The current was a bit higher than its normal
value. The impeller was re-machined again to reduce
its diameter and the assembly was tested again. The
vibration and temperature sensors were reinstalled in
their place and the vibration analysis was performed
using RESM.
Results of Vibration Analysis
The results of the vibration analysis indicated an
increase in the level of vibrations in the pump and
motor system CP-BOM-01, in particular the amplitude of the first harmonics of the fundamental rotational frequency of the system increased. However
the values are probably within the acceptable limits,
considering the uncertainties in the measurements of
tolerances in eccentricities, balancing and alignment
of the assembly. In the case of pump and motor system CP-BOM-02 the result obtained from vibration
analysis was quite satisfactory, however it was not
possible to determine accurately the diameter of the
impeller, which would be most efficient with respect
to its pumping power and a consequent increase in
the flow rate of the pump, as the circuit does not
have adequate instrumentation, which would permit
accurate determination of the diameter of impeller.
• Substitution of the motor-rotor thrust bearing
and rotor balancing
• Substitution of pump shaft bearing
• Soldering and machining of pump shaft
• Substitution of seal ring bushing to correct the
alignment in the bearing box
• Substitution of bearing of the flywheel
During remounting of motor and pump assembly it
was found necessary to re-machine the impeller of the
pump and to carry out overall balancing of the assembly along with shaft and new bearing. After remounting the motor and pump assembly were submitted to
tests, at normal operational regime, by measuring the
motor current, which was found close to its normal
value. The vibration and temperature sensors were
re-installed in their usual positions and the analysis
of vibration was performed using RESM.
Maintenance of pump CP-BOM-02
The second pump also indicated the need for some
repair work since vibration analysis indicated in this
case also an unusual noise level, probably due to problems in the bearings. When the assembly was dismounted it became clear that not only the bearings,
References
[1] Open-Pool Research Reactor – Instruction Book,
The Babcock and Wilcox Co, 1957.
[2] IEA-R1 Research Reactor, Safety Analysis Report, 1999.
73
[3] Manual of Operation and Maintenance of Research Reactor IEA-R1.
[4] Methods and Technologies of
(MTM), Report - 80098, 2000.
74
Maintenance
Software for the preventive maintenance program of
IEA-R1 reactor equipment
A. V. Leite, C. L. Wen, E. L. Benevenutti, G.F. Maciel, M. O.Martins, M. Yovanovich, M.R. Carvalho,
E.N.B. Santos
The IEA-R1 research reactor is a swimming pool
type reactor using ordinary water as moderator and
coolant and beryllium and graphite as reflector. The
reactor was constructed by Babcock & Wilcox and
became critical in the September of 1957. The reactor is presently operating at 2MW with 64 hours
continuous per week cycle. The reactor staff consists
of three distinct groups:
of maintenance work needed in each case. The subroutine also furnishes information about the maintenance plan and permits equipment data update. The
maintenance plan consists of a collection of technical
instructions (TI) as well as periodicity, for the maintenance of all of reactor equipment. The information
refers to individual equipment as well as systems composed of various equipments. Tasks described in TIs
are written in a manner that facilitates its execution
by the technician by distributing maintenance activities in compatible periodicities. Updated information
and equipment register consultation is handled by the
“Update” subroutine, for all reactor equipment. This
data bank contains the following information: a brief
description, manufacturer, model, series, equipment
code and the localization of equipment in the reactor
building. The subroutine permits the inclusion, data
correction or exclusion of register as well as elaboration of report for simple reference. The “Update” is
also responsible for generating the information chart
of the maintenance history of the equipment. The
subroutine is divided in three parts:
Preventive maintenance program - relates equipment
and their respective maintenance plan, periodicity,
date of next maintenance and technician responsible
for carrying out the maintenance work.
• Reactor operation
• Equipment and system maintenance (mechanical, electrical, electronics)
• Technical support
Considering the process of implantation of the
Quality Management Program at the Research Reactor Center for obtaining ISSO 9001-2000 certification
in the “Operation and maintenance of the IEA-R1 research reactor and irradiation services” and also considering the future upgrade of the reactor operation
regime, from 60 hours per week at 2MW to 120 hours
per week at 5MW, to produce the radioisotopes 99 Mo
and 131 I, used in medical applications, in our reactor,
a preventive and corrective maintenance as well as
calibration program for major reactor equipment is
being implemented[1]. In order to handle a large flux
of information resulting from this program software
was developed, in collaboration with the Information
Technology Center of IPEN, to manage the System
of Preventive and Corrective Maintenance and Calibration (SPCMC) for reactor equipment. Implementation of this software will be carried out in three
stages:
Maintenance information chart- the program generates information chart for the maintenance of each
equipment or system. The charts are numbered and
printed for execution by the designated technician.
After the task is concluded, the technician makes a
report for data bank update.
Information chart follow up- the program updates
the data bank using the information on the job execution status report, for example solicited, executed,
pending, cancelled etc. This is the time when the
unexpected occurrences during the maintenance are
registered, identifying the person responsible for the
maintenance job and the date. This information is
very important, as they will result in the maintenance
history report containing all information about preventive maintenance carried out in each equipment
or system and is crucial for the prediction of future
corrective maintenance.
The software for Preventive Maintenance Routine
(PMR) has been in operation since 2001 and is giving good results. The versatility of the routine, which
makes it quite powerful, is the possibility of running the program in Windows environment and its
implantation in the Network “internet” or “intranet”
• Preventive Maintenance Routine (PMR)
• Corrective Maintenance Routine (CMR)
• Equipment Calibration and Checking Routine
(ECCA)
The preset work describes details of the Preventive Maintenance Routine. The minimum necessary
configuration for executing the PMR is a personal
computer model Pentium, compatible with window
environment. The routine PMR has various levels of
access and presents detailed reports of all the proposed and executed maintenance jobs as well as the
history of each equipment during its useful lifetime.
The programming language used was DELPHI5[2].
PMR is divided in two subroutines: “Register” and
“Update”. The subroutine “Register” contains a bank
of technical data for every equipment and the details
75
permitting information sharing. It is important to
emphasize that PMR is only a part of the more
comprehensive System of Preventive and Corrective
Maintenance and Calibration (SPCMC) which, when
completely implemented will permit control and retraceability of information related to the maintenance
of reactor equipment in a manner that will permit
predictive actions and avoid unnecessary equipment
losses and replacements and consequent interruption
in the reactor operation.
References
[1] Manual of routine operation and maintenance of
the reactor IEA-R1.
[2] S. Teixeira , DELPHI5, Developers Guide, 2001
76
Neutronic and thermohydraulic calculations of the reactor
IEA-R1
V.G. Rodrigues, T.N. Conti
The IEA-R1 research reactor is a swimming pool
type reactor and its main applications are: radioisotope production for medical and industrial applications, material testing, neutron irradiation services,
basic and applied research in physics, chemistry, biology and engineering and training for reactor operators. The reactor physics group at the Research Reactor Center offers important contribution for the operation of the reactor by calculating neutronic and thermohydraulic parameters such as fuel burn-up, neutron flux distribution, power density, reactivity gain
when the reactor core configuration is changed, temperature distribution in the fuel element, distribution
of pressure along the cooling channels, calculations of
departure nucleate boiling reactor (DNBR) and onset
nucleate boiling (ONB) In this report we present the
calculated total burn-up of 235 U in the fuel elements
as of December 2002. In addition the temperature
distribution in the center of the fuel element as well
as on the surface of the fuel cladding for the hottest
channel is also presented. It should be emphasized
that the core of the IEA-R1 reactor was originally
designed for 30 fuel elements of the MTR type (26
standard elements and 4 control elements) with beryllium and graphite reflectors. All the irradiation and
material testing positions are located in the reflectors. The actual configuration of the reactor (configuration No. 211) nucleus contains 24 standard fuel
elements, 4 control elements and 1 central irradiation
element of beryllium (EIBE). The standard fuel elements consist of 18 fuel plates with dimensions of
62.5cm x 7.7cm x 0.15cm (60cm x6.04cm x 0.76cm
being active dimensions of the uranium) cladded in
aluminum. The control elements have the same dimension as the standard fuel elements but have only
12 fuel plates. The neutronics calculation methodology for the reactor IEA-R1 is based on the programs
LEOPARD[1, 2] and HAMMER-TECHNION[3] for
generating the cross sections, the program 2DB[4] for
calculating the reactivity and fuel burn-up in 2-D and
the program CITATION[5] for calculating the reactivity of the control rods in 3-D. The history of the
reactor operation is simulated with the program2DB
in 2-D without control rods. After the change of core
configuration the reactivity gain is calculated with
the program CITATION in 2-D without control rods.
Figure 1 shows the 235 U burn-up in each element of
the nuclear core in the month of December 2002. It
should be mentioned that the oldest element in the
core is No. 149 introduced in the June of 1996.
30
percent of U-235 burnup
25
20
15
10
5
0
150
155
160
165
170
175
180
number of burned fuel elements
Figure 1: U-235 burnup (percentage), core configuration 211 with Be reflectors.
The program model COBRA-3C[6] was used for
the calculations of thermohydraulics. The analysis
was based on the nominal conditions of the reactor
operation. The present calculations did not consider
the uncertainties in the nuclear and geometric measurements of the conservative model. The analysis
utilized the conditions closest to the real operation of
the reactor. The entrance temperature of the cooling
fluid was taken as 36o C with the flow rate of 3000
gpm. The analysis refers to the hottest channel, with
reactor operating at the power of 2MW.
Figure 2 shows the axial distribution of the temperature at the center of the fuel and at the surface
of the cladding with maximum temperature values at
the lower end of the fuel element reaching 89 o C and
71 o C. respectively. We calculated the minimum departure nucleate boiling reactor (MDNBR) including
Labuntsoy correlation (an option in the COBRA program), indicating a large margin in relation with the
critical heat flux. It can be concluded that from the
point of view of the neutronics and thermohydraulics
the operation of the reactor at 2MW does not violate
any operational limits
77
26, Westinghouse Electric Corporation, September 1963.
[2] W. Kerr, J.S. King, J.C. Lee, W.R. Martin and
D.K. Wehe, The Ford nuclear reactor demonstration project for the evaluation and analysis of
low enrichment fuel - final report”, Argonne National Laboratory, Argonne, ANL/RERTR/TM17, July 1991.
[3] J. Barhen, W. Rhotenstein and E. Taviv, The
HAMMER Code System Technion, Israel Institute of Technology, Haifa, Israel, NP-565, 1978.
[4] W.W. Little Jr, R.W. Hardie, “2DB user’s manual
- revision I”, BNWL-831, REVI, Battelle Pacific
Northwest Laboratory, 1969.
Figure 2: Axial distribution of the temperature at the
center of the fuel and at the surface of the cladding.
[5] T.B. Fowler, D.R. Vondy, G.W. Cunningham
“Nuclear reactor core analysis code: CITATION”,
Oak Ridge National Laboratory, ORNL-TM2496, Rev. 2, Suppl. 3, July 1972.
References
[6] COBRA-3C/RERTR - A thermal-hidraulic Subchannel Code with Low PressureCapabilities and
Suppliment-Argone National Laboratory (1983).
[1] R.F.Barry “LEOPARD - a spectrum dependent non-spatial depletion code”, WCAP-3269-
78
Area monitoring and radiation dose in the IEA-R1 reactor
building
R.B.Lemes, E.Y.Toyoda, C.A.R. Costa, V.M. Lopes, R.N. Carvalho
During the operation of the reactor IEAR1, the
Radiation Protection Staff carries out, several activities including monitoring, of work place. In particular
these measurements are made in the 3rd floor (the hall
at the upper level of pool), and 1st floor of the reactor building where most of the equipment for physics
experiments are installed in the beam-holes. A group
of 12 Radiation Protection Officers included among
them supervisors and technicians carry out these activities working in three shifts of 8 hours each during
the 64 hours continuous operation of the reactor per
week. The health physics personnel belong to the Nuclear Safety and Radiation Protection group of IPEN
and are specially designated to work in this facility.
The main objective of the routine area monitoring in
the reactor building is to verify if the working conditions are safe all the time as required by the article
12 of the Safety Analysis Report[1]. The result of
the workplace monitoring could be used to evaluate
the individual dose according to a model, which takes
into account the activities of each worker (during the
reactor maintenance and operation). The individual
dose estimated in this manner, can be compared to
the dose obtained by individual thermo-luminescence
dosimetry[2]. The locations selected for routine monitoring at pool top level are representative of the places
normally used by the reactor operators for different
types of operations like sample loading for irradiation and its removal after irradiation. On the 1st
floor, the locations are chosen near beam-holes and
where unloading of irradiated samples are carried out.
The workplace monitoring is carried out always at
the same locations with monitors held at the same
height from the floor (approximately 100 cm). Monitoring is done during the reactor operation and two
separate measurements are carried out in each shift.
Measurements are made for gamma radiation as well
as for neutrons using appropriate detectors and the
dose rate is recorded in a logbook. An average of neutron and gamma dose rate is computed at the end of
each reactor operation cycle. Routine radiation monitoring is carried out at 25 different locations in the
reactor building. Figures 1 shows average monthly
dose rates measured during the year 2002, at some of
the principal locations on the 3rd floor of the reactor
where most of the routine operations are carried out.
The dose represents mainly the gamma dose since the
neutron dose rate near the pool surface is negligible.
Gamma Dose: 3
rd
floor
A
160
B
C
120
m
Dose Rate ( Sv/h)
D
80
40
2
4
6
8
10
12
Month (2002)
Figure 1: Monthly average gamma dose rates on the
3rd floor with reactor operating at 2 MW.
Neutron + Gamma Dose: 1
200
st
floor
m
Dose Rate ( Sv)/h
150
100
F
G
H
I
50
0
2
4
6
8
10
12
Month (2002)
Figure 2: Monthly average gamma dose rates on the
1st floor with reactor operating at 2 MW.
It can be seen from these figures that at some locations the dose rates are well above the derived limit
of 25 µ Sv/h for 2000 hours of work in a year[3]. The
presence of workers in these locations without previous knowledge of the radiation levels certainly would
have resulted in much higher equivalent dose received
than established by the radiation protection regulations as well as established by Safety Analysis Report
(SAR). From the periodic workplace monitoring at
various locations as well as controlled use of these locations by the people working in the reactor building
it has been possible to keep the actual dose received
by them to levels much bellow the established limits.
Figure 3 shows the annual dose received as a function of number of workers. The relevant information
Figure 2 shows the monthly average dose rate (neutron and gamma) measured during the year 2002 at
various points near neutron beam-holes located in the
1st floor of the reactor building with reactor operating
a 2MW.
79
during removal of irradiated samples. They are also
responsible for supervising the dispatch of irradiated
samples to different installations as well as to other
institutions outside IPEN The Radiation Protection
Staff gives support during the change of reactor core
configurations, preventive maintenance of reactor systems and decontamination of components. They also
give support to the associated laboratories, of the Research Reactor Center, working with radioactive material, like radiochemistry, nuclear physics and nuclear metrology laboratories. It can be concluded
therefore that radiation monitoring performed at various locations in the reactor building is fulfilling its
purpose, which is to guarantee, the safe working conditions, and to evaluate the external radiation exposure received by each worker It can be noticed that
the external dose received by the large majority of
the workers is below the recording level of 0.2 mSv
per month[3].
was obtained from the data on individual external
dosimetry.
35
30
m
o
N of Workers
25
20
15
0.2
10
5
0.7
0.4
0.9
1.1
0
Dose m Sv/h
Figure 3: Annual dose received by the workers inside
the reactor building during year 2000. The minimum
measurable dose m is < 0.2 m Sv.
References
[1] Safety Analysis Report of the IEA-R1 Research
Reactor, 1996, (internal report)
The Radiation Protection Officers of the Research
Reactor Center have additional task-related monitoring activities during the reactor operation period.
These include monitoring during introduction of samples, to be irradiated in the reactor core, in different
irradiation devices through reactor pool as well as
[2] International commission of radiation protection
(ICRP) edition 35
[3] CNEN NE3.01 norms
80
Implementation of a quality management system at the
Research Reactor Center
Tereza C. Salvetti e Rosemeire P. Paiva
tation generation and implementation, internal and
external audits, management reviews, continuous improvement in all process phases and a systematic involvement and training of all related personnel. Furthermore, the significant role-played by regulatory requirements as well as the importance of operating
a nuclear facility within suitable environmental and
safety polices were taken in account.
The documentation system that supports the QMS
is composed of approximately 150 documents including quality manual, business and action plans, operational procedures and work instructions. In addition to these there are documents related to the
reactor safety, such as the IEA-R1 Safety Analysis
Report, and those related to corporative activities
that support the Integrated Management System of
ipen. All documents are available at quality site at
ipen’s intranet. Two internal and two external audits
were carried out after the QMS implementation. The
first external audit was just for system implementation diagnostics. Fundação Carlos Alberto Vanzolini
(FCAV) carried out external audits on 19/08/2002
and 25/11/2002. This process resulted in the accreditation (number 2610) of the Operation and Maintenance of the IEA-R1 Reactor and Irradiation Services by Fundação Carlos Alberto Vanzolini
on December 13, 2002. The accreditation is nationally and internationally recognized. The effective implantation of the QMS at CRPq can be considered
a milestone in the history of this reactor considering
the fact that there are very few nuclear reactors in the
world that have ISO certification. The whole process
would not have been possible without the CRPq staff
involvement and collaboration as well as the cooperation of the personnel in charge of the corporative
processes at ipen.
As the business becomes more and more competitive many organizations are looking forward to improve their activities by means of quality management
systems (QMS) implementation in order to carry out
their missions according to specified objectives and
to survive to commercial pressures. The implementation of QMS aims to achieve determined objectives
with resource and cost optimization. Improvement
is focused in the process. As a consequence of this
improvement, products or services with quality, competitive cost and agility will result in satisfied clients.
In this context, the Research Reactor Center
(CRPq) at ipen, following directives established by
the institution, started in 2001the process of implementation of a QMS in compliance to NBR ISO 9001
version 2000. This system was also designed to comply with the requirements of other appropriate standards of various activities carried out by CRPq such
as: NBR ISO/IEC 17025: 2001(General requirements
for the competence of testing and calibration laboratories), CNEN IN-001 1994 (Certificação do Atendimento aos Requisitos de Segurança e Radioproteção
pelas Instalações Nucleares e pelas Instalações Radiativas) e CNEN NN 1.16 1999 (Garantia da Qualidade
para a Segurança de Usinas Nucleoelétricas e Outras
Instalações).
The system plan was influenced by various factors: revision of standards NBR ISO 9000 series, reevaluation of previous documents written before the
system implementation, definition of processes to be
documented, revision and implementation of corporative processes which are applicable to CRPq and
personnel stimulus towards quality concepts. The
methodology applied in the implementation of the
QMS included: Quality Policy identification, responsibility definition, task distribution, QMS documen-
81
Calibration of a Self Powered Neutron Detector
SPND/Rhodium in the IEA-R1 Research Reactor by
Means of Activation Foils
Walter Ricci Filho, Mauro S. Dias, Julio B. M. Tondin, Marina F. Koskinas
The objective of the present work is to install a
simple, practical and reliable instrument in the IEAR1 reactor for mapping the neutron flux. With the
increasing demand for the production of radioisotopes
for medical application in Brazil it became necessary to optimize the methodology for neutron flux
measurements at different irradiation positions in the
reactor[1, 2].
The method selected for neutron flux measurement
is based on the use of a self-powered neutron detector
(SPND) with Rh as emitter. In the previous Progress
Report (1999-2000) the first part of this experiment
was described. The present experiment aims to determine the relationship between the SPND response
and the absolute flux measurement performed with
activation foils by means of 197 Au(n,γ)198 Au reaction.
A total of 78 gold foils, 39 bare and 39 cadmium covered were irradiated for 60 min.. Shelves 2, 5 and 8
were chosen for irradiation positions 24A, 24B, 34A,
34B, 36A, 36B, 65A, 65B e 58, and shelves 2, 6, 10,
14, 18 e 22 for positions 52 e 72 (see Figure 1).
ations. Additional measurements were performed at
5 MW. For a well thermalized neutron field (epithermal coefficient around 0.03), the SPND current can
be related with the thermal neutron flux by means of
the following equations:
Ime
(g + rs)Sme )
(14)
Ime
(1.025 + 0.03 × 7.375) × 421
(15)
ΦT h =
ΦT h =
ΦT h = Ime × 2.01 × 1020
(16)
where: ΦT h is the thermal neutron flux, Ime is
the SPND current, Sme is the SPND thermal neutron
sensitivity (Ampere/neutron), and g, s and r are the
Wescott factors[3].
The value indicated in equation (2) for the thermal
neutron sensitivity was taken from the manufacturer
specifications. The correction factor related to emitter burn-up[1] has been neglected because in the
present experiment the SPND device was used for
the first time. A least square fitting was performed
between the neutron flux obtained by foil activation
and the SPND current response (see figure 2). The
results for the intercept (a) and the slope (b) were
respectively:
a = (2,37 ± 0,11) x 1020 e b = -(9,9 ± 7,6)x 1011 .
The estimated uncertainty of the SPND current was
10%, based on variations in readings for the same irradiation position at different reactor operation days.
For the flux determination by activation foils, the
dominant contribution to the uncertainty is the thermal self-shielding factor, estimated around 10%.
Figure 1: Schematic of reactor grid plate.
Thermal and epithermal neutron fluxes were measured. The neutron flux scanning using the SPND
device was started immediately after gold foil irradiation. The reactor operated at 2 MW for most irradi82
With these parameters it is possible to reproduce the
neutron flux measured by the activation foils with an
uncertainty of 10% (one standard deviation). New
measurements are planned covering the SPND detector with cadmium in order to verify possible epithermal contribution in the detector response.
10
.s
-1
)
8
References
4
[1] Walter Ricci Filho, Análise do Elemento de Irradiação de Berílio no Reator IEA-R1 São Paulo
1998 (Dissertação de Mestrado IPEN).
2
[2] V. Surkov Determinação da sensibilidade de
detectores auto-energizados (SPDs), São Paulo
1994. (Dissertação de Mestrado IPEN).
Neutron Flux (10
13
n.cm
-2
6
0
0
1
2
3
4
[3] C.H. Westcott, Effective Cross Section Values
for Well-Moderated Thermal Reactor Spectra,
Atomic Canada Limited. Report AECL-1101,
EANDC(Can)-4, TNCC(Can)-30, Chalk River,
Ontario, September, 1960.
5
-7
SPND current (10 A)
[4] B.T. Kena and B.H. Van Domelen, Neutron Activation: Relationship of Sample Mass to SelfShielding Factor. Int. J. Appl. Rad. and Isotopes,
17 (1966) 47-50
Figure 2: Relationship between the measured neutron
flux and the SPND response.
Considering the self shielding factor due to the
presence of the SPND in the neutron field[4, 5], the
coefficients become:
a = (3,55 ± 0,16) x 1020 e b = -(1,1 ± 1,2)x 1012 .
[5] N.P. Baumann, Resonance integrals and selfshielding factors for detector foils, Report DP817, January, 1963.
83
Publications
Publications
9. K. A. Fonseca, M.F. Koskinas, M. S. Dias, Disintegration Rate Measurement of a 192 Ir Solution, Applied Radiation and Isotopes,
54(2001)141.
Papers published in Journals
1. A. C. Junqueira, R. Dogra, A. W. Carbonari, R.
N. Saxena, J. Mestnik-Filho, M. Moralles, Measurement of Quadrupole Interactions in LaMO3
(M = Cr, Fe, Co) Perovskites by TDPAC, Hyperfine interactions 136(2001)509.
10. K. Shimamura, S.L. Baldochi, I.M. Ranieri,
H. Sato, T. Fujita, V.L. Mazzocchi, C.B.R.
Parente, C.O. Paiva-Santos, C.V. Santilli, N.
Sarukura, T. Fukuda, Crystal growth of Cedoped and undoped LiCaAlF6 by the Czochralski technique under CF4 atmosphere, Journal
of Crystal Growth 223(2001)383.
2. A. W. Carbonari, W. Pendl Jr., J. MestnikFilho, R. N. Saxena, PAC Measurements on
New Ferromagnetic Compound Pd2 TiSn, Hyperfine Interactions 133(2001)83.
11. L. G. Shpinkova, A. W. Carbonari, S. M.
Nikitin, J. Mestnik-Filho, TDPAC studies of
DTPA complexes with 111 In and 111m Cd, Acta
Physica Polonica 100(2001)799.
3. A.W. Carbonari, H. Haas, Lattice Site Dependence of Cd Hyperfine Field in Pd2 MnSn
Heusler Alloy., Hyperfine Interactions
133(2001)71.
12. M. Olzon-Dionysio, S. D. Souza, A. P. Ayala, A. W. Carbonari, E. Longo Concentration dependence of the Electric Field Gradient
in PbZr1−x Tix O3 ceramics, Hyperfine Interactions 136(2001)523.
4. A.W. Carbonari, J. Mestnik-Filho Saxena, R.
Dogra , J. A. H. Coaquira, Hyperfine Interactions in CeT2 Ge2 (T = Mn, Co) Heavy
Fermion Compounds Measured By TDPAC,
Hyperfine interactions 136(2001)345.
13. M. V. Lalic, J. Mestnik-Filho, A. W. Carbonari,
R. N. Saxena, H. Haas Study of Hyperfine Fields
in CeIn3 by Electronic Structure Calculations,
Hyperfine interactions 136(2001)743.
5. C.B.Zamboni, J.A.G.Medeiros, A.L.Lapolli,
S.P.Camargo, F.A.Genezini, M.T.F da Cruz,
Energy levels in 139 La from the decay of
139
Ba, Applied Radiation and Isotopes
55(2001)447.
14. M.F. Koskinas, D. Simões, M.S. Dias, Measurement of the gamma-ray probability per decay
of 42 K, Applied Radiation and Isotopes,
54(2001)443.
6. J.A.G Medeiros, C.B.Zamboni, M.T.F.da Cruz,
Decay of 72 Ga, Applied Radiation and Isotopes 54(2001)245.
15. N. L. Maidana, M.S. Dias, M. F. Koskinas, Measurement of the thermal neutron
capture cross section and resonance integral
of 241 Am, Radiochimica Acta, Munchen,
89(2001)419.
7. J.D.T. Arruda-Neto, V.P. Likhachev, G.P.
Nogueira, G.W. Araujo, S.P. Camargo, G.T.
Cavalcante, A.C. Cestari, A.M. Craveiro, A.
Deppman, J.W. Ferreira F, F. Garcia, L.P. Geraldo, F. Guzmán, O.M. Helene, M.V. Manso,
M.N. Martins, J. Mesa, M.F. Oliveira, G.
Perez, O. Rodriguez, M.V. Tavares, V.R. Vanin,
Transfer coefficient measurements of uranium
to the organs of Wistar rats, as a function of
the uranium content in the food, Applied Radiation and Isotopes 54(2001)947.
16. R. Dogra, A. C. Junqueira, R. N. Saxena, A.
W. Carbonari, J. Mestnik-Filho, M.Moralles,
Hyperfine interactions mesurements in LaCrO3
and LaFeO3 perovskites using perturbed angular
correlation spectroscopy, Physical Review B
63(2001)224104.
17. A. W. Carbonari, J. Mestnik-Filho, R. N. Saxena, H. Saitovitch, Investigation of hyperfine interactions in CeIn3 by TDPAC, Hyperfine Interactions 133(2001)77.
8. J.Y.Z. Chávez, M. T. F. da Cruz, M. N. Martins, V.P.Likhachev, C. B. Zamboni, S. P. Camargo, J.A.G.Medeiros, M.M.Hindi. Response
function of a Germanium detector to photon energies between 6 and 120 keV, Nuclear Instruments and Methods 457(2001)212.
18. A. R. Aguir, M. Saiki, Determination of trace
elements in human nail clippings by neutron
85
activation analysis, J. Radioanal.
Chem. 249(2001)413.
Nucl.
Brazil, Geostandards Newslettter: The
Journal of Geostandards and Geoanalysis 25(2001)307.
19. I. M. C. Camargo, C. C. C. Zoppe, M. Saiki, M.
B. A. Vasconcelos, Evaluation of the precision
in the dentifrice abrasivity measurements obtained by a radiotracer method, J. Radioanal.
Nucl. Chem. 249(2001)487.
28. M. B. A. Vasconcellos, P. Bode, A. K. Ammerlaan, M. Saiki, G. Paletti, M. G. M. Catharino,
D. I. T. Fávaro, R. Baruzzi, D. A. Rodrigues,
Multielemental hair composition of Brazilian
Indian populational groups by instrumental neutron activation analysis, J. Radioanal. Nucl.
Chem 249(2001)491.
20. M. Saiki, L. K. Horimoto, M. B. A. Vascocellos, M. P. Marcelli, D. M. B. Coccaro, Survey of
elemental concentrations in lichen samples collected from Sãooo Paulo State, J. Radioanal.
Nucl. Chem. 249(2001)317.
29. R. M. Latini, A. V. Bellido Jr., M. B. A. Vasconcellos, O. F. Dias Jr., Classificação de Cerâmicas Arqueológicas da Bacia Amazônica, Quíimica Nova 24(2001)724.
21. L. K. Adachi, M. Saiki, T. N. Campos, An
in vitro investigation of human enamel wear
by restorative dental materials, J. Radioanal.
Nucl. Chem 249(2001)465.
30. R. M. Piasentin, M. J. A. Armelin, O. Primavesi, M. Saiki, Effects of fertilizer with different mineral composition on the absorption of
Ca, Cu, K, Mg, Mn, Na and V, by two cultivars of pigeonpea Cajanus Cajan, Millps, J.
Radioanal. Nucl. Chem. 249(2001)83.
22. I. M. C. Camargo, M. Saiki, M. B. A. Vasconcellos, D. M. Ávila, Abrasiveness evaluation of silica and calcium carbonate used in the
production of dentifrices, J. Cosmet. Sci.
52(2001)163.
31. M. J. A. Armelin, R. L. Ávila, R. M. Piasentin, M. Saiki, Application of neutron activation analysis to evaluate the health status of
equines by means of Cu, Fe, Mn and Zn determinations in their hair, J. Radioanal. Nucl.
Chem. 249(2001)417.
23. I. Costa, M. C. L. Oliveira, H. Takiishi,
M. Saiki, R. N. Faria, Corrosion behaviour
of commercial NdFeB magnets-The effect of
magnetization, Key Engineering Materials
189/191(2001)340.
32. I. L. Cunha, L. Bueno, D. I. T. Fávaro, V. A.
Maihara, S. M. F. Cozzolino, Analysis of 210 Pb
e 210 Po in Brazilian food and diets, J. Radioanal. Nucl. Chem. 247(2001)447.
24. M. Saiki, S. O. Rogero, I. Costa, O. V. Correa, O. Z. Higa, Characterization of ear piercing studs and their corrosion products by neutron activation analysis, J. Radioanal. Nucl.
Chem. 248(2001)133.
33. V. A. Maihara, D. I. T. Fávaro, V. N. Silva,
I. B. Gonzaga, V. L. Silva, I. L. Cunha, M. B.
A. Vascocellos, S. M. F. Cozzolino, Analysis of
mineral constituents in duplicate portion diets
of two university student groups by instrumental neutron activation analysis, J. Radioanal.
Nucl. Chem. 249(2001)21.
25. J. C. Wasserman, A. M. G. Figueiredo, F. Pellegati, E. V. Silva-Filho, Elemental composition of sediment cores from a mangrove environment using neutron activation analysis, J.
Geochem. Explor. 72(2001)129.
34. D. I. T. Fávaro, E. Chicourel, V. A. Maihara, K. C. Zangrande, M. I. Rodriguez, L.
G. Barra, M. B. A. Vasconcellos, S. M. F.
Cozzolino, Evaluation of some essential and
trace elements in diets from 3 nuseries from
Juiz de Fora, MG, Brazil, by neutron activation analysis, J.Radioanal. Nucl. Chem.
249(2001)15.
26. A. M. G. Figueiredo, M. Saiki, R. B. Ticianelli, M. Domingos, E. S. Alves, B. Markert, Determination of trace elements in Tillandsia usneoides by neutron activation analysis for
environmental biomonitoring, J. Radioanal.
Nucl. Chem. 249(2001)391.
27. F. Pellegati, A. M. G. Figueiredo, J. C. Wasserman, Neutron activation analysis applied to the
determination of heavy metals and other trace
elements in sediments from Sepetiba Bay (RJ),
35. F. E. Larizzatti, D. I. T. Fávaro, S. R. D.
Moreira, B. P. Mazzilli, E. L. Piovano, Multi86
elemental Determination By Instrumental Neutron Activation Analysis And Recent Sedimentation Rates Using Pb-210 Dating Method At
Laguna Del Plata, Cordoba, Argentina, J. Radioanal. Nucl. Chem 249(2001)263.
44. M. V. Lalic, J. Mestnik-Filho, A. W. Carbonari, R. N. Saxena, M. Moralles, Influence of Cd imputity on the electronic properties of CuAlO 2 delafossite: first-principles calculations, Jouranl of Physics: Condensed
Matter 14(2002)5517.
36. S. M. B. Oliveira, A. J. Melfi, A. H. Fostier, M. C. Forti, D. I. T. Fávaro, R. Boluet,
Soils as an important sink for mercury in the
Amazon, Water, Air and Soil Pollution
26(2001)321.
45. M. F. Koskinas, K. A. Fonseca, M. S. Dias,
Disintegration rate measurement of a 152 Eu
solution, Applied Radiation and Isotopes
56(2002)441.
37. S. L. Petroni, M. A. F. Pires, C. S. Munita,
Radiotracer Technique in Adsorption Study of
Zinc and Cadmium on Peat, Journal Trace
and Microprobe Techniques 19(2001)429.
46. M. S. Dias, J. R. Sebastião, M. F. Koskinas, Methodology for monitoring the residual
activity in silicon rods irradiated with thermal
neutrons, Applied Radiation and Isotopes
57(2002)801.
38. C. S. Munita, R. P. Paiva, P. M. S. Oliveira, E.
F. Momose, R. Plá, M. Moreno, O. Andonie, F.
Falabella, L. Munoz, I. Konenkamp, Intercomparison among three Activation Analysis Laboratories in South America, Journal Trace and
Microprobe Techniques 19(2001)189.
47. R. Pugliesi, M. A. S. Pereira, Study of the
Neutron Radiography Characteristics for the
Solid State Nuclear Track Detector MakrofolDE, Nuclear Instruments and Methods in
Physics Research A 484 (2002)613.
48. R. M. Castro, V. R. Vanin, O. A. M. Helene,
R. Pascholati, M. S. Dias, M. F. Koskinas,
The correlations between the emission probabilities of the more intense gamma rays in 152 Gd
and 152 Sm following 152 Eu decay, Journal of
Nuclear Science and Technology, Supplement 2(2002)485.
39. C. S. Munita, R. P. Paiva, M. A. Alves, P. M.
S. Oliveira, E. F. Momose, Major and Trace
Element Characterization of Prehistoric Ceramic from Rezende Archaeological Site, J. Radioanal. Nucl. Chem. 248(2001)93.
40. G. Gozzi, A. Costa, S. H. Tatumi, E. F. Momose, C. S. Munita, R. P. Paiva, Study of the
Thermoluminescent and Optical Stimulated Luminescence Properties of Quartz Crystal, Radiation Effects and Defects in Solids
154(2001)347.
49. A. F. Barreto, F. H. Bezerra, K. Suguio,
S. H. Tatumi, E. F. Momose, R. P. Paiva,
C. S. Munita, Late pleistocene marine terrace sequences in northeastern Brazil: sea-level
change and tectonic implications, Palaeogeography, Palaeoclimatology, Palaeoecology
179(2002)57.
41. L. G. Shpinkova, A. W. Carbonari, S. M.
Nikitin, J. Mestnik-Filho, Influence of electron capture after-effects on the stability of
111
In(111 Cd)-complexes with organic ligands,
Chemical Physics 279(2002)255.
50. A. M. G. Figueiredo, W. Avristcher, E. A.
Masini, S. C. Diniz, A. Abrão, Determination
of lanthanides (La, Ce, Nd, Sm) and other elements in metallic gallium by instrumental neutron activation analysis, Journal of Alloys
and Compounds 344(2002)36.
42. M. N. Takeda, M. S. Dias, M. F. Koskinas. Cascade summing corrections for HPGe spectrometers by the Monte Carlo Method, Applied Radiation and Isotopes 56(2002)105.
51. A. J. G. Santos, B. P. Mazzilli, D. I. T. Fávaro,
Characterization of stockpilled phosphogypsum
waste in Santos basin, Brazil, Radiopretection - Colloques 37, C1(2002)1307.
43. M. V. Lalic, J. Mestnik-Filho, A. W. Carbonari,
R. N. Saxena, H. Haas, First-principles Calculations of Hyperfine Fields in the CeIn3 , Physical Review B 65(2002)0544051.
52. M. Saiki, M. C. Silva, R. Fulfaro, M. B. A.
Vasconcellos, Study on instrumental neutron
87
activation analysis of aluminium in geological and biological reference materials, Journal of Trace and Microprobe Techniques,
20(2002)517.
Dieta dos Servidores do Instituto Nacional de
Pesquisas da Amazônia, Manaus, AM, Brasil,
Acta Amazônica 32(2002)267.
61. E. P. Soares; E. C. D. Nunes, M. Saiki,
H. Wiebeck, Caracterização de políimeros e
determinação de constituintes inorgânicos em
embalagens plásticas metalizadas, Políimeros:
Ciência e Tecnologia 12(2002)206.
53. J. M. Bastidas, M. Saiki, S. O. Rogero, I.
Costa, J. L. Polo, An electrochemical study of
the behaviour of ear piercing studs immersed
in a culture médium, J. App. Electrochem
32(2002)487.
54. M. J. A. Armelin, R. M. Piasentin, O. Primavesi, Neutron activation analysis applied to
determine zinc in forages used in intensive
dairy cattle production systems, J. Radioanal.
Nucl. Chem. 252(2002)585.
Papers accepted for publication in Journals
1. M. V. Lalic, J. Mestnik-Filho, A. W. Carbonari,
R. N. Saxena, Changes induced by the presence
of Zn or Ni impurity at Cu sites in CuAlO2 delafossite, Solid Sate Communications.
55. M. B. A. Vasconcellos, M. G. M. Catharino, G.
Palletti, M. Saiki, P. Bode, D. I. T. Fávaro,
R. Baruzzi, D. A. Rodrigues, Determination of
mercury and selenium in biological samples by
neutron activation analysis. Journal of Trace
and Microprobe Techniques 20(2002)527.
2. M. N. Rao, J. R. B. Oliveira, W. A. Seale, M. A.
Rizzutto, R. V. Ribas, J. A. Alcantara, Nuñes,
D. Pereira, N. Added, E. W. Cybulska, N. H.
Medina, R. N. Saxena., A. W. , Carbonari, Installation of the IMPAC technique in the Pelletron Laboratory, Braz. J. Physics.
56. D. F. Matos, E. F. de Lima, C. A. Sommer, L.
V. S. Nardi, J. D. de Liz, A. M. G. Figueiredo,
R. Pierosan, B. L. Waichel, Riolitos neoproterozóicos pós-colisionais na área do Santuário,
Sul do Brasil: litogeoquíimica, quíimica mineral
e origens das heterogeneidades texturais. Revista Brasileira de Geociências 32(2002).
3. A.M. Baccarelli, M.S. Dias, M.F.Koskinas, Coincidence System for Standardization of Radionuclides Using a Plastic Scintillator Detector, Applied Radiation And Isotopes.
4. M.S. Dias, M.F.Koskinas, Standardization of a
Tl-204 Radioactive Solution, Applied Radiation and Isotopes.
57. O. Primavesi, A. C. P. A. Primavesi, M. J.
A. Armelin, Qualidade mineral degradabilidade
potencial de adubos verdes conduzidos sobre
latossolos, na região tropical de Sãooo Carlos, Sp, Brasil, Revista de Agricultura 77
(2002)89.
5. M. O. Menezes, R. Pugliesi, M. A. S. Pereira,
M. L. G. Andrade, Real-Time Neutron Radiography Using a Plastic Scintillator Detector,
Braz. J. Physics.
6. M. M. A. Medeiros, C. B. Zamboni, F. A.
Zenezini, J. A. G. Medeiros, M.T.F da Cruz,
J.Y. Zevallos-Chávez, Excited levels in 149 Pm
from the decay of 149 Nd, Applied Radiation
and Isotopes.
58. P. M. Vasconcelos, A. T. Onoe, K. Kawashita,
A. J. Soares, W. Teixeira, 40 Ar/39 Ar
Geochronology at the Instituto de Geociencias, USP : instrumentation, analytical procedures and calibration. Anais da Academia
Brasileira de Ciências 74(2002)297.
7. J. A. H. Coaquira, H. R. Rechenberg, J.
Mestnik-Filho and A. W. Carbonari, Structural, magnetic and hyperfine properties of
Zr(Cr1−x Fex )2 hydrides, Journal of Alloys
and Compounds.
59. L. K. Yuyama, J. P. Aguiar, D. Silva Filho, K.
Yuyama, D. I. T. Fávaro, M. B. A. Vasconcellos,
Açai como fonte de ferro: mito ou realidade?,
Acta Amazônica 32(2002)521.
8. N. M. Sumita, M. E. Mendes, M. Macchione, E.
T. Guimarães, A. J. F. Lichtenfels, D. A. Lobo,
P. H. N. Saldiva, M. Saiki, Tradescantia pallida
(Rose) Hunt cv. purpurea Boom in the characterization of air pollution by accumulation of
60. D. Nagahama, L. K. Yuyama, J. P. Aguiar, S.
M. Macedo, L. Yonekura F. Alencar, D. I. T.
Fávaro, C. Afonso, M. B. A. Vasconcellos, Composição Quíimica e Percentual de Adequação da
88
trace elements, Journal of the Air & Waste
Management Association.
3. M. Saiki, S. O. Rogero, I. Costa, E. R. Alves,
O. V. Correa, E. Dantas, Analysis of metallic
biomaterials of medical interest and their corrosion products, J. Radional. Nucl. Chem.
9. E. R. Alves, N. M. Sumita, P. H. N. Saldiva
INAA applied to the study of Tradescantia pallida plant for environmental pollution monitoring, Czechoslovak Journal of Physics.
4. N. M. Sumita, M. Saiki, P. H. N. Saldica, Analysis of Tradescantia pallida plant exposed in different sites for biomonitoring purposes, J. Radional. Nucl. Chem.
10. S. O. Rogero, M. Saiki, M. C. L. Oliveira, I.
Costa, Corrosion performance and cytoxicity of
sintered Nd-Fe-B magnets. Journal Materials Science.
5. M. K. Takata, M. Saiki, INAA of cortical and
trabecular bone samples from animals, J. Radional. Nucl. Chem.
6. S. M. B. Oliveira, F. E. Larizzatti, D. I. T. Fávaro, S. R. D. Moreira, B. P. Mazzilli, E. L. Piovano, Rare earth element patterns in lake sediments studied by neutron activation analysis, J.
Radional. Nucl. Chem.
11. S. M. B. Oliveira, J. H. Larizzatti, D. I. T.
Fávaro, Comportamento do Mercúrio e outros elementos-traço em Solos Lateríiticos da
Províincia Auríifera do Tapajós, Geoquíimica
Brasiliensis.
7. M. J. A. Armelin, R. L. Ávila, R. M. Pisentin,
M. Saiki, Chelated mineral supply effect evaluation on horses by Cu, Fe, K, Mn and Zn determinations in their hair, J. Radional. Nucl.
Chem.
12. O. Primavesi, R. M. Piasentin, M. J. A.
Armelin, A. C. Primavesi, Caracterização multielementar de insumos agríicolas, em sistema
intensivo de produção animal, pelo método de
análise por ativação com nêutrons, Revista de
Agricultura.
8. A. M. G. Figueiredo, A. L. Alcalá, R. B. Ticianelli, M. Domingos, M. Saiki, The use of
Tillandsia usneoides L. as bioindicator of air
pollution in Sãoo Paulo, Brazil, J. Radioanal.
Nucl. Chem.
13. C. S. Munita, R. P. Paiva, M. A. Alves, P. M.
S. Oliveira, E. F. Momose, Provenance study of
archaeological ceramic, Journal of Trace and
Microprobe Techniques.
9. M. B. A. Vasconcellos, M. Saiki, D. I. T. Fávaro,
V. A. Maihara, A. M. G. Figueiredo, Neutron
activation analysis at the research Reactor Center of IPEN / CNEN-SP - Biological and environmental applications, J.Radioanal. Nucl.
Chem.
14. M. Yee, S. H. Tatumi, K. Suguio, A. F. Barreto,
E. F. Momose, C. S. Munita, R. P. Paiva, Thermoluminescence (TL) dating of inactive dunes
from the Rio Grande do Norte Coastal, Brazil,
Journal Coastal Research.
10. E. G. Moreira, M. B. A. Vasconcellos, M. Saiki,
Instrumental neutron activation analysis applied to the chemical composition of metallic
materials with study of interferences, J. Radional. Nucl. Chem.
15. K. Suguio, S. H. Tatumi, E. A. Kowata, C. S.
Munita, R. P. Paiva Upper pleistocene deposits
of the Comprida Island (São Paulo State) dated
by Thermoluminescence Method. Academia
Brasileira de Ciências
11. V. A. Maihara, V. L. Silva, D. I. T. Fávaro, M.
B. A. Vasconcellos, I. B. Gonzaga, S. M. F. Cozzolino, Daily intake Selenium of selected Brazilian population groups, J. Radional. Nucl.
Chem.
Papers submitted for publication
1. M. T. F. da Cruz, J. Y. Zevallos-Chávez, F.
A. Genezini, Z. O. Guimarães Filho, V. P.
0Likhachev, M. N. Martins, J. A. G. Medeiros,
J. C. O. Morel, P. R. Pascholati, C. B. Zamboni, Analysis of γ γ angular correlation experiments performed with a multi-detector system,
Brazilian Journal of Physics.
12. D. I. T. Fávaro, D. Mafra, V. A. Maihara, M. B.
A. Vasconcellos, S. M. F. Cozzolino, Evaluation
of Zn and Fe in diets of patients with chronic
reanal failure, J. Radional. Nucl. Chem.
13. E. L. Piovano, F. E. Larizzatti, D. I. T. Fávaro, S. M. B. Oloveira, S. R. D. Moreira, B. P.
Mmazzilli, D. Arizetegui, The geochemical response to 20th century environmental changes
in Laguna Mar Chiquita (Córdoba, Argentina),
The Science of the Total Environment.
2. M. S. Dias, V. Cardoso, V. R. Vanin, M. F.
Koskinas, Combination of Nonlinear Function
and Mixing Method for Fitting HPGe Efficiency
Curve in the 59-2754 keV Energy Range, Applied Radiation And Isotopes.
89
Conference Proceedings
"Condensed Matter Studies by Nuclear Methods", 14-19 May 2001, Zakopane, Poland, p.60.
8. M.V. Manso, A.N. Gouveia, A. Deppman, V.P.
Likhachev, O.A.M. Helene, V.R. Vanin, J.
Mesa, J.D.T. Arruda-Neto, C.B. Zamboni, M.
Saiki, G.P. Nogueira, A.C. Cestari, S.P. Camargo, O. Rodriguez, F. Guzman, F. Garcia.
Microdistribution and localized dosimetry of
238
U in beagle bones. VII Workshop of Nuclear Physics Havana , Cuba, Oct. 23-26, 2001
(CDROM).
1. A.M. Baccarelli, M.S. Dias, M.F. Koskinas,
Standardization of 241 Am by means of coincidence system using 4[f070] plastic scintillator detector.
In: V Regional Congress
on Radiation Protection and Safety Regional
IRPA CONGRESS, 2001, Recife. V Regional
Congress on Radiation Protection and Safety
Proceedings. Recife: Sociedade Brasileira de
Proteção Radiológica, 2001. v. 1, p. 1-3
(CDROM).
9. M.F. Koskinas; W. O. Lavras; M.S. Dias; K.A.
Fonseca Primary Standardization of 51 Cr Radioactive Solution. In: V Regional Congress
on Radiation Protection and Safety Regional
IRPA CONGRESS, 2001, Recife. V Regional
Congress on Radiation Protection and Safety
Proceedings. Recife: Sociedade Brasileira de
Proteção Radiológica, 2001. v. 1, p. a)3
(CDROM).
2. C.B. Zamboni, K. Shtejer, G.S. Zahn, A.M.G.
Figueiredo, T. Madi-Filho, L. Dalaqua Jr.,
R.B. Lima, T. Daltron. A neutron irradiator to perform nuclear activation. Proceedings:
3rd NURT, Havana -Cuba, 4p, 2001 (CDROM).
3. C.B. Zamboni, K. Shtejer, G.S. Zahn, A.M.G.
Figueiredo, T. Madi-Filho, L. Dalaqua Jr., R.B.
Lima, T. Daltron. A neutron Irradiator to
perform nuclear activation. 3rd International
Symposium on Nuclear and Related techniques,
(Nurt-2001), Havana-Cuba, Oct. 22-26, 2001
(CDROM).
10. M.T.F. da Cruz, J.Y. Zevallos-Chávez,F.A.
Genezini,
Z.O. Guimarães-Filho,
V.P.
Likhachev, M.N. Martins, J.A.G. Medeiros ,
J.C.O. Morel, P.R. Pascholati, C.B. Zamboni.
Analysis of γγ angular correlation experiments
performed with a multi-detector system. Proceedings: International Nuclear Physics conference, July 30 - August 3, University of California, Berkeley USA, 5 p, 2001.
4. J.D.T. Arruda-Neto, C.B. Zamboni, C.L.
Duarte, R. Semmler, S.A.C. Jorge, G.W.
Araujo, K. Shtejer, A.N. Gouveia, A. Deppman,
O.A.M. Helene, V.R. Vanin, V.V. Manso, A.
Miranda, O. Rodriguez Effects of gamma Radiation on the pBs-KS DNA plasmid. 3rd International Symposium on Nuclear and Related techniques, (Nurt-2001), Havana-Cuba, Oct. 22-26,
2001 (CDROM).
11. N.L. Maidana; M.S. Dias; M.F. Koskinas.
Primary standardization of 242 Am radioactive
sources. In: V Regional Congress on Radiation Protection and Safety Regional conference
IRPA, 2001, Recife. V Regional Congress on
Radiation Protection and Safety Proceedings.
Recife: Sociedade Brasileira de Proteção Radiológica, 2001. v. 1, p. a)3 (CDROM).
5. J.D.T. Arruda-Neto, A. Deppman, V.P.
Likhachev, A.N. Gouveia, O. A.M. Helene, V.R.
Vanin, J. Mesa, E. Alves, F. Bringas, M.V.
Manso, J.W. Pereira-Filho, K. Shtejer, C.L.
Duarte, R. Semmler, C.B. Zamboni, S.A.C.
Jorge, G.W. Araújo, A. Miranda, O. Rodriguez,
F. Guzman Estudio de daños inducidos en
DNA por la radiación: propuesta de proyecto
temático y multidisciplinario. Proceedings: IV
WONP, Havana-Cuba , 4p, 2001 (CDROM).
12. P. Perso, N. Added, R.M. Castro, M.T.F. da
Cruz, ,F.A. Genezini, V. P. Likhachev, M.N.
Martins, J.A.G. Medeiros , J.C.O. Morel, E.
Nascimento, E.B. Norman, V.R. Vanin, C.B.
Zamboni, J.Y. Zevallos-Chávez. 102 Rhm : could
it be a cosmic-ray chronometer? Proceedings:
International Nuclear Physics conference, July
30 - August 3, University of California, Berkeley
USA, 6 p , 2001.
6. J.D.T. Arruda-Neto, C.B. Zamboni, C.L.
Duarte, R. Semmler, S.A. C. Jorge,
G.W.Araújo, K. Shtejer, A.N. Gouveia, A.
Deppman, O.A.M. Helene, V.R. Vanin, V.P.
Likhachev, M.V. Manso, A. Miranda, O. Rodriguez. Effects of gamma radiation on the
pBs-KS DNA plasmid. IV WONP, HavanaCuba, 5p, 2001(CDROM).
13. M. Saiki, L.K. Horimoto, M.B.A. Vasconcellos,
M.P. Marcelli, N.M. Sumita, P.H.N. Saldiva Determination of trace elements in lichen samples
by instrumental neutron activation analysis. In:
co-ordinated research project meeting: Validation and application of as biomonitors of trace
element atmospheric pollution, analyzed by nuclear and related techniques, Mar 20-24, 2000,
Vienna, Austria, Report ... p. 65-79, 2001 (
NAHRES-63).
7. L.G. Shpinkova, A.W.Carbonari, S.M. Nikitin,
J. Mestnik-Filho. Influence of electron capture after-effects on (111 In-111 Cd)-DTPA integrity. XXXVI Zakopane School of Physics
90
14. M. saiki, A.R. Aguiar Sodium and chlorine determinations in nails of healthy and cystic fibrosis children. In: 3rd International symposium on trace elements in human: New perspectives, Atens, Greece, Oct, 4-6 2001, Proceedings Book , p. 529-538, 2001.
Colloquium, 11 a 15 de novembro de 2001em
Gramado, Rio Grande do Sul, Proceedings,
CD-ROM, p. 1792-1795, 2001.
23. S.O. Rogero, I. Costa, M. Saiki Estudo dos
produtos de corrosão de brincos perfurantes.
In: V Encontro Nacional de Aplicações Nucleares,ENAN, 15-20 October, 2000, Rio de
Janeiro, RJ, Anais , Rio de Janeiro, 2001,
CD-ROM.
15. D.T. Nardi, M. Saiki, M.B.A. Vasconcellos,
Caracterização de componentes inorgânicos em
suplementos minerais pelo método de análise
por ativação com nêutrons. In: V Encontro
Nacional de Aplicações Nucleares, ENAN, Oct
15-20, 2000, Rio de Janeiro, RJ, Anais , CDROM, 2001.
24. A.M.G. Figueiredo, M. Saiki, J.E.S. Sarkis,
M.H. Kakazu, I. Karmann Determinação de
urânio em dentes de Toxodon platensis do Alto
Ribeira (São Paulo) para datação. In: V
Encontro Nacional de Aplicações Nucleares,
ENAN, 15-20 October , 2000, Rio de Janeiro,
RJ, Anais , CD-ROM, 2001.
16. L.K. Adachi, M. Saiki, T.N. Campos Avaliação
do efeito da irradiação na dureza do esmalte
dental e dos materiais odontológicos. In:V
Encontro Nacional de Aplicações Nucleares,
ENAN, Out 15-20, 2000, Rio de Janeiro, RJ,
Anais , Rio de Janeiro, 2001, CD-ROM.
25. A.P. Rebeiro, A.M.G. Figueiredo, J.B. Sígolo
Determinação de metais pesados e outros elementos em sedimentos lacustres da Estação de
Tratamento de Esgoto de Barueri por ativação
neutrônica. In:V Encontro Nacional de Aplicações Nucleares,ENAN, 15-20 October, 2000,
Rio de Janeiro, RJ, Anais , CD-ROM, 2001.
17. L.K. Horimoto, M. Saiki, M.B.A. Vasconcellos, M.P. Marcelli Análise de liquens para
uso na monitoração da poluição ambiental.
In: V Encontro Nacional de Aplicações Nucleares,ENAN, Out 15-20, 2000, Rio de Janeiro,
RJ, Anais , Rio de Janeiro, 2001, CD-ROM.
26. A.M.G. Figueiredo, M. Saiki, R.B. Ticianelli,
M. Domingps, E.S. Alves, M.P. Marcelli Determinação de elementos terras raras em biomonitores por ativação neutrônica. V Encontro de
Aplicações Nucleares, In: V Encontro Nacional
de Aplicações Nucleares,ENAN, 15-20 October,
2000, Rio de Janeiro, RJ, Anais , CD-ROM,
2001.
18. M.K. Takata, M. Saiki Análise por ativação
com nêutrons de tecidos ósseos medular e cortical. da determinação de alumínio pelo método
de análise por ativação com nêutrons . In:
V Encontro Nacional de Aplicações Nucleares,
ENAN, Out 15-20, 2000, Rio de Janeiro, RJ,
Anais , Rio de Janeiro, 2001, CD-ROM.
27. C.B. Zamboni, A.M.G. Figueiredo, F.A.
Genezini, A.C. Cestari, J.D.T. Arruda-Neto
Nuclear methodology to study kidney anomalies. In: V Encontro Nacional de Aplicações
Nucleares,ENAN, 15-20 October , 2000, Rio de
Janeiro, RJ, Anais , CD-ROM, 2001.
19. A.M. Kamiya, R. Fulfaro, M. Saiki Avaliação
da migração de elementos químicos das embalagens plásticas para alimentos. In: V Encontro
Nacional de Aplicações Nucleares, ENAN, Out
15-20, 2000, Rio de Janeiro, RJ, Anais , Rio
de Janeiro, 2001, CD-ROM.
28. A.P. Ribeiro, A.M.G. Figueiredo, J.B. Sígolo
Ativação neutrônica aplicada à análise de sedimentos lacustres da Estação de Tratamento de
Esgoto de Barueri, São Paulo, Brasil. In: VI
Congresso de Geoquímica dos Países de Língua
Portuguesa / XII Semana de Geoquímica, Faro,
Portugal, 2001, Actas, 670-673, 2001.
20. M. Saiki, D.T. Nardi Characterisation of inorganic components in multimineral/mineral supplements. In: 3rd International symposium on
trace elements in human: New perspectives,
Athens, Greece, Oct, 4-6 2001, Proceedings,
p. 398-405, 2001.
29. C.P.R. Morcelli, A.M.G. Figueiredo, J. Enzweiler Análise por ativação com nêutrons instrumental dos elementos do grupo da platina e
ouro em materiais de referência após fuSãoo coletora com sulfeto de níquel. In: VI Congresso
de Geoquímica dos Países de Língua Portuguesa
/ XII Semana de Geoquímica, Faro, Portugal,
2001, Actas, 665-669, 2001.
21. E.P. Soares, M. Saiki, H. Wiebeck Análise de
elementos químicos e tipos de polímeros em materiais plásticos metalizados In: 56O Congresso
Anual da Associação Brasileira de Metalurgia
e Materiais, Anais.. ,CD-ROM, p.601-611,
2001.
22. E.P. Soares, E. Cássia, D. Nunes, M. Saiki,
H. Wiebeck Identificação de polímeros e constituintes inorgânicos em embalagens plástio
cas metalizadas., In: 6 Congresso Brasileiro
de Polímeros/ IX International Macromolecular
30. A.M.G. Figueiredo, M.B.A. Vasconcellos, D.
Piccot, C.A. Nogueira, D.I.T. Fávaro, M. Saiki
k0-NAA implementation and application at
neutron activation analysis laboratory, IPEN,
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Sãoo Paulo, Brazil. In: 3rd International Symposium on Nuclear and Related Techniques, Havana, Cuba, 2001, Proceedings, CD ROM,
2001.
growth of PbI2 crystals. Dependence of the radiation response on PbI2 crystal purity. In: Nuclear Symposium , Nov. 04-10, 2001, San Diego,
USA, CD-ROM.
31. E.G. Moreira, M.B.A. Vasconcellos, Análise
por ativação com nêutrons instrumental aplicada ao estudo da composiçào química de
aços .In: V Encontro Nacional de Aplicações
Nucleares,ENAN, 15-20 October, 2000,Rio de
Janeiro,R.J., Anais,2001.1 CD-ROM.
39. C.S. Kira, V.A. Maihara, Determinação de Na,
Cl, Ca, Mg, Mn e K em amostras de leite por
análise por ativação. In:V Encontro Nacional
de Aplicações Nucleares, ENAN, Oct. 15-20,
2000, Rio de Janeiro, RJ, Anais , CD-ROM,
2001
32. M.G.M. Catharino, M.B.A Vasconcellos, P.
Bode, R. Baruzzi, D.A. Rodrigues Determinação de mercúrio e selênio em materiais biológicos pelo método de análise por ativação
com nêutrons. In: V Encontro Nacional de
Aplicações Nucleares, 15-19 October ,2001, Rio
de Janeiro ,R.J., Anais, ABEN, 2001, CDROM.
40. Saito, R.T. Saito, I.L. Cunha, V.A. Maihara, FÁVARO, D.I.T. Fávaro, S.M.F. Ozzolino
Análise de 210 Pb e 137 Cs em Dietas de estudantes universitários. In: V Encontro Nacional
de Aplicações Nucleares, ENAN, Oct 15-20,
2000, Rio de Janeiro, RJ, Anais , CD-ROM,
2001
41. D.R. Arine, D.I.T. Fávaro, S.M.B. Oliveira
Determinação Multielementar em Amostras de
Sedimentos da região de Ipero´, SP, por Absorção Atômica e Ativação Neutrônica. In:
V Encontro Nacional de Aplicações Nucleares,
ENAN, Oct. 15-20, 2000, Rio de Janeiro, RJ,
Anais , CD-ROM, 2001
33. M.B.A. Vasconcellos, M.G.M. Catharino, G.
Paletti, M. Saiki, P. Bode, D.I.T. Fávaro, R.
Baruzzi, D.A. Rodrigues Determination of mercury and selenium in biological samples by neutron activation analysis. In:3rd International
symposium on trace elements in human: New
perspectives, 4-6 October ,2001,Athens,Greece,
Proceedings,Athens, 2001
42. D.I.T. Fávaro, S.R.D. Moreira, V.A. Campos,
B.P. Mazzilli, F. Campagnoli Determinação
Multielementar Por Ativação Neutrônica De
Sedimentos Do Reservatório Billings, Braço Rio
Grande, São Paulo. In: V Encontro Nacional
de Aplicações Nucleares, ENAN, Oct. 15-20,
2000, Rio de Janeiro, RJ, Anais , CD-ROM,
2001.
34. M.J.A. Armelin, R.M. Piasentin, O. Primavesi
Monitoração do Arsênio em sistemas intensivos
de produção de gado pela análise por ativação
com nêutrons. In: V Encontro Nacional de
Aplicações Nucleares, ENAN, Nov 15-20, 2000,
Rio de Janeiro, RJ, Anais , CD-ROM, 2001.
35. R.M. Piasentin, M.J.A. Armelin, O. Primavesi Análise de elementos tóxicos em duas
variedades de Guandu (Cajanus Cajan (L.)
Millsp), cultivadas em solos tratados, por ativação com nêutrons. In:V Encontro Nacional
de Aplicações Nucleares,ENAN, Nov. 15-20,
2000, Rio de Janeiro, RJ, Anais , CD-ROM,
2001
43. F.E. Larizzatti, D.I.T. Fávaro, S.M.B. Pliveira,
S.M.D. Moreira, B.P. Mazzilli, E.L. Piovano
Caracterização Geoquímica e Mineralógica de
Sedimentos das Lagunas Del Plata e Mar Chiquita, Província de Córdoba, Argentina. In; VI
Congresso de Geoquimica dos países de lingua
Purtuguesa, April 9-12, 2001, Faro, Portugal,
Actas, p. 321-325, 2001.
36. I.B. Oliveira, M.J.A. Armelin, M.M. Hamada
Desenvolvimento do detector semicondutor de
Iodeto de Chumbo. In: V Encontro Nacional
de Aplicações Nucleares, ENAN, Nov. 15-20,
2000, Rio de Janeiro, RJ, Anais , CD-ROM,
2001
44. P.S.C. Silva, B.P. Mazzilli, D.I.T. Fávaro Estudo dos Elementos Terras Raras em Sedimentos do Estuário de Santos e São Vicente. In:
VIII Congresso Brasileiro de Geoquímica, October 21-23, 2001, Curitiba, Pr, Anais , CDROM 2001.
37. M.J.A. Armelin, O. Primavesi, R.M. Piasentin,
A.G. Silva Estudo comparativo das concentrações de Ca, Cl, K, Mg, Mn e Na em algumas gramíneas forrageiras cultivadas em diferentes tipos de solo. In: 38a. Reunião anual da
sociedade Brasileira de Zootecnia, Jul. 23-26,
2001, Piracicaba, SP, Anais .
45. J.D.T. Arruda-Neto , A.C. Cestari, G.P.
Nogueira , L.E.C. Fonseca, C.B. Zamboni, M.
Saiki, M.V. Manso, J. Mesa, V.R. Vanin, O.
A.M. Helene, A. Deppman, V.P. Likhachev,
A.N. Gouveia, S.A.C. Jorge , M.N. Martins Observação de interferência metabólica acentuada
na biocinética de urânio em ossos de frangos de
corte. VI ENAN, Rio de Janeiro, August 11-16,
2002 (CDROM).
38. I.B. Oliveira, F.E. Costa, M.J.A. Armelin,
L.P. Cardoso, M.M. Hamada Purification and
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46. J.A.H. Coaquira, H.R. Rechenberg, J. MestnikFilho, A.W. Carbonari "Structural,magnetic
and hyperfine properties of Zr(Cr a)x Fe x ) 2 hydrides". International Symposium on Metal
Hydrogen Systems, Annecy, França, 2-6 september 2002
IPEN/CNEN-SP In: VI Encontro Nacional de
Aplicações Nucleares, ENAN, Rio de Janeiro,
Brazil, 11-16 August, 2002 (CDROM).
56. L.C. Campos, C.B.R. Parente, V.L. Mazzocchi,
O. Helene Determination of the β-quartz cell
parameters using NMD azimuthal angular differences. Anais do XV Congresso Brasileiro de
Engenharia e Ciência dos Materiais, Natal, RN,
novembro de 2002 (CDROM).
47. C.A. Federico, L.P. Geraldo, O.L. Gonçalez, R.
Semmler, A.D. Caldeira, L.S.Y. Rigolon Estudo
do equilíbrio eletrônico no alumínio utilizando
o dosímetro termoluminescente de CaSO4 :Dy,
VI Encontro Nacional de Aplicações Nucleares,
ENAN Rio de Janeiro, August 11-16, 2002
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57. L.C. Oliveira, C.B. Zamboni, A.C. Cestari,
L. Dalaqua Jr., M.V.G. Manso, A.M.G.
Figueiredo, J.T. Arruda-Neto Nuclear methodology for studying biological functions of mammalians submitted to uranium ingestion.VI
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48. C.B.R. Parente, V.L. Mazzocchi, Y.P. Mascarenhas O Novo Difratômetro de Nêutrons
do IPEN-CNEN/SP. Anais do XV Congresso
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58. M.F. Koskinas, W.O. Lavras e M.S. Dias Primary standardization of 153 Sm radioactive solution. In VI Encontro Nacional de Aplicações
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49. F. Brancaccio, M.S. Dias Sistema Eletrônico
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M.S. Pereira. Real-time neutron radiography at
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da Física Nuclear no Brazil. São Pedro 09/2002.
61. P. Perso, N. Added, R.M. Castro, M.T.F. da
Cruz, F. A. Genezini, V.P. Likhachev, M.N.
Martins, J.A.G. Medeiros , J.C.O. Morel, E.
Nascimento, E.B. Norman, V.R. Vanin, C.B.
Zamboni, J.Y. Zevallos-Chávez. 102m Rh: could
it be a cosmic-ray chronometer? AIP Conference Proceedings 610 (2002) 437.
51. G.S. Zahn, C.B. Zamboni, L.C. Oliveira, F.A.
Genezini, M.T.F. da Cruz, J.Y. ZevallosChávez, H. Dias Gamma Spectroscopy of Excited Levels in 193 Ir.
VI Encontro Nacional de Aplicações Nucleares, ENAN, Rio de
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52. G.S. Zahn, R.B. Lima, T. Madi-Filho, C.B.
Zamboni Neutron flux distribution in an Am-Be
neutron Irradiator. VI Encontro Nacional de
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August 11-16, 2002 (CDROM).
62. C.S. Kira, V.A. Maihara Estudo comparativo
na determinação de elementos essenciais em
amostras de produtos lácteos por AANI e ICPAES. In: VI Encontro Nacional de Aplicações
Nucleares, ENAN, Rio de Janeiro, RJ, August
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53. I.M.M.A. Medeiros, C.B. Zamboni, J.A.G. de
Medeiros, F.A. Genezini, M.T.F. da Cruz , J.Y.
Zevallos-Chávez Spin of Excited levels in 149 Pm
. VI Encontro Nacional de Aplicações Nucleares, ENAN, Rio de Janeiro, August 11-16,
2002 (CDROM).
63. S.L.G. Petroni, M.A.F. Pires, C.S. Munita
Cinêtica de adsorção de Cu em turfa. In:
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ENAN Rio de Janeiro, RJ, 11-16 August, 2002,
Anais.CD-ROM, 5 pgs.
54. J.A.G. Medeiros, F.A. Genezini ,C.B. Zamboni Estudo da Estrutura nuclear do 72 Ge.
VI Encontro Nacional de Aplicações Nucleares
ENAN, Rio de Janeiro, August 11-16, 2002
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64. V.A. Maihara, I.M. Sato, D.I.T. Fávaro, V.L.
Salvador, M.B.A. Vasconcellos Aplicação das
técnicas de Análise por Ativação com Nêutrons
e Fluorescência de Raios-X em Amostra de Fígado Bovino In: VI Encontro Nacional de Aplicações Nucleares, ENAN Rio de Janeiro, RJ,
11-16, August 2002, Anais.CD-ROM.
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em solos por ativação neutrônica e fluorescência
de raios X. In:VI Encontro Nacional de Aplicações Nucleares, ENAN Rio de Janeiro, RJ,
11-16 August 2002, Anais.CD-ROM, 2002.
73. F. Fuga; M. Saiki, M.B.A. Vasconcellos, N.H.
Honda, O.S. Siqueira Análise de espécies de
liquens epifíticos para uso na biomonitoração
de poluentes atmosféricos. In:VI Encontro Nacional de Aplicações Nucleares, ENAN, 11-16
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66. C.A. Nogueira, A.M.G. Figueiredo, J.B. Sígolo
Distribuição de elementos metálicos em sedimentos de drenagens do Parque Estadual da
Ilha Anchieta, SP. In: VI Encontro Nacional de
Aplicações Nucleares, ENAN, Rio de Janeiro,
RJ, 11-16 August 2002, Anais.CD-ROM, 2002.
74. M. Saiki, S.O. Rogero, I. Costa, E. Dantas,
M.C.L. Oliveira Characterization of corrosion
products from nd-fe-b magnets used in dental
prostheses. In: VI Encontro Nacional de Aplicações Nucleares, ENAN ,11-16 August, 2002,
Rio de Janeiro, RJ, CDROM.
67. A.P. Ribeiro, A.M.G. Figueiredo, J.B. Sígolo,
R.C.L. Figueira Aplicação da NAA no estudo
do comportamento geoquímico de elementos de
interesse em sedimentos lacustres de uma estação de tratamento de esgoto. In:VI Encontro
Nacional de Aplicações Nucleares, ENAN Rio
de Janeiro, RJ, 11-16 August 2002, Anais.CDROM, 2002.
75. A.C.A. Vaz, M. Saiki Avaliação da influência
das propriedades e geometria da amostra em
espectrometria de raios gama. In: VI Encontro
Nacional de Aplicações Nucleares, ENAN, 1116 August, 2002, Rio de Janeiro, RJ,CDROM.
76. M.K. Takata, N.M. Sumita, P.H.N. Saldiva,
C.A. Pasqualucci, M. Saiki Determinação de
elementos traço em tecido ósseo humano pelo
método de ativação com nêutrons. In: VI
Encontro Nacional de Aplicações Nucleares,
ENAN , 11-16 August, 2002, Rio de Janeiro,
RJ, CDROM.
68. J.C. Wasserman, A.M.G. Figueiredo, A.L.
Figueira, A.A. Kelecom preliminary study on
the behaviour of trace elements in sediment
cores from Ilha Grande (Rio de Janeiro) by
neutron activation analysis. In:VI Encontro
Nacional de Aplicações Nucleares, ENAN Rio
de Janeiro, RJ, 11 a 16 de Agosto 2002,
Anais.CD-ROM, 2002.
77. E.P. Soares, M. Saiki, H. Wiebeck Determinação de elementos tóxicos em materiais plásticos metalizados. In: VI Encontro Nacional de
Aplicações Nucleares, ENAN, 11-16 Ago, 2002,
Rio de Janeiro, RJ, Anais do VI ENAN, Rio de
Janeiro, RJ, 2002, CDROM.
69. M.I.O. Eiras, FÁVARO, D.I.T. Fávaro, M.
Ribeiro, S.M.F. Cozzolino Determinação de Elementos Minerais e Traços em Dietas pela Técnica de Ativação Neutrônica. In: VI Encontro
Nacional de Aplicações Nucleares, ENAN Rio
de Janeiro, RJ, 11-16 August 2002, Anais.CDROM, 2002.
78. E.M. Adachi, M.N. Youssef, M. Saiki Avaliação
da perda dental humana com o uso do clareador
peróxido de carbamida comparado ao condicionamento com ácido fosfórico- método radiométrico. In: VI Encontro Nacional de Aplicações Nucleares, ENAN, 11-16 August, 2002,
Rio de Janeiro, RJ, CDROM.
70. P.S.C. Silva, B.P. mazzilli, D.I.T. Fávaro
Distribuição Vertical de Elementos Menors e
Traços por Análise por Ativação Neutrônica Instrumental nos Sedimentos do Estuário de Santos e São Vicente, São Paulo, Brasil. In:VI
Encontro Nacional de Aplicações Nucleares,
ENAN Rio de Janeiro, RJ, 11-16 August 2002,
Anais.CD-ROM, 2002.
79. M.J.A. Armelin, O. Primavesi Aplicação da
análise por ativação com nêutrons para determinação de Ferro em forrageiras usadas no sistema
intensivo de produção de bovinos de leite. In:
VI Encontro Nacional de Aplicações Nucleares,
ENAN , 11-16 Auhust, 2002, Rio de Janeiro,
RJ, CDROM.
71. S. Avino, M. Saiki, R. Fulfaro Determinação
de elementos traço nos fitofármacos ginseng e
ginkgo biloba. In: VI Encontro Nacional de
Aplicações Nucleares, ENAN , 11-16 August,
2002, Rio de Janeiro, RJ, CD-ROM, 6 pgs.
80. I.B. Oliveira, M.J.A. Armelin, M.M. Hamada
Purificação por refinamento zonal para
preparação dos detectores semicondutores de
PbI2 e TlBr. In: VI Encontro Nacional de
Aplicações Nucleares, ENAN , 11-16 August,
2002,Rio de Janeiro, RJ, CDROM
72. A.K. Tavaraya, M. Saiki, N.M. Sumita, P.H.N.
Saldiva Análise por ativação com nêutrons
da planta Tradescantia pallida para uso na
monitoração de poluentes atmosféricos. In:VI
Encontro Nacional de Aplicações Nucleares,
ENAN, 11-16 August, 2002, Rio de Janeiro, RJ,
CD-ROM, 5 pgs.
81. M.G.M. Catharino, M.B.A. Vasconcellos Determinação de selênio em materiais biológicos por
análise por ativação com nêutrons. Comparação estatística entre o uso do 77M Se (t1/2 =
94
17,45s) e 75 Se (t1/2 =119,8d). In: VI Encontro
Nacional de Aplicações Nucleares, ENAN, Rio
de Janeiro/RJ, 11-16 August 2002. CD-ROM
2. C.A. Frederico, W.J. Vieira, L.S.Y. Rigolon,
O.L. Gonçalez, L.P. Geraldo, R. Semmler. Medidas Experimentais da Taxa de Energia Absorvida e Comparação com cálculos utilizando
fatores de dose e transporte de elctrons no
código MCNP. Relatório Técnico da Faculdades
SENAC de Ciências Exatas e Tecnologia - RT
01/2001.
82. E.G. Moreira, M.B.A. Vasconcellos, M. Saiki,
C.O. Iamashita Determinação de elementos
traço em materiais de referência de silício
e ferro-silício, pelo método instrumental de
análise por ativação com nêutrons.
In:VI
Encontro Nacional de Aplicações Nucleares,
ENAN , Rio de Janeiro/RJ, 11-16 August 2002.
CD-ROM
3. O. Primavesi, L. A. Correa, A. C. Primavesi, H.
Cantarella, M. J. A. Armelin, A. G. Silva, A. R.
Freitas, Adubação com uréia em pastagem de
Cynodon dactylon cv. Coastcross sob manejo
rotacionado: eficiência e perdas, Embrapa
Pecuária do Sudeste Circular Técnica n.
30, 2001.
83. J. R. Oliveira, A. J. Soares, Desenvolvimento
de um Programa Computacional para Estudo
do Sistema de Controle do Reator em Plantas
PWR, In: XIII Encontro Nacional de Física de
Reatores ENFIR, Rio de Janeiro, 11 -16 August
, 2002 (CDROM)
Conference Contributions
84. M. B. Garcia, A. J. Soares, B. D. Baptista
Filho ”Utilização de Cintiladores Plásticos em
Sistemas de Detecção Sensíveis à Posição, In:
VI Encontro Nacional de Aplicações Nucleares
ENAN, Rio de Janeiro, 11-16 August, 2002
(CDROM).
International Conferences
1. L.G. Shpinkova, A.W.Carbonari, S.M. Nikitin,
J. Mestnik-Filho. Influence of electron capture
after-effects on 111 In(111 Cd)-DTPA integrity.
XXXVI Zakopane School of Physics "Condensed Matter Studies by Nuclear Methods",
May 14-19, 2001, Zakopane, Poland.
85. A.V. Leite, E.L.Benevenutti, G.F. Maciel,
M.O. Martins, M. Yovanovich, M.R. Carvalho,
E.N.B. Santos; Manutenção corretiva nas Bombas do Circuito Primário do Reator IEA-R1,
In: VI Encontro Nacional de Aplicações Nucleares ENAN, Rio de Janeiro, 11-16 August,
2002 (CDROM).
2. M.N. Takeda, M.S. Dias, M. F. Koskinas. ”Cascade summing correction for HPGe spectrometers by the Monte Carlo method”. 13th International Conference on Radionuclide Metrology and its Applications, ICRM’2001, May 1418, 2001, Braunchweig, Germany, Book of Abstracts, 089.
86. A.V. Leite, E.L.Benevenutti, G.F. Maciel,
M.O. Martins, M. Yovanovich, M.R. Carvalho,
E.N.B. Santos, Software de Manutenção Preventiva dos Equipamentos do Reator IEA-R1,
In: VI Encontro Nacional de Aplicações Nucleares ENAN, Rio de Janeiro, 11-16 August,
2002 (CDROM).
3. M.F. Koskinas, K.A. Fonseca, M.S. Dias. Disintegration rate measurement of 152 Eu solution.
13th International Conference on Radionuclide
Metrology and its Applications, ICRM’2001,
May 14-18, 2001, Braunchweig, Germany, Book
of Abstracts, 090.
87. José Patricio N. Cárdenas, Christovam R.
Romero Filho, Um sistema para monitoração
remota dos níveis de radiação no prédio do
reator IEA-R1 no caso de uma emergência radiológica , In: VI Encontro Nacional de Aplicações Nucleares ENAN, Rio de Janeiro, 11-16
August, 2002 (CDROM).
4. C.S. Munita, R.P. Paiva, M.A. Alves, P.M.S.
oliveira, E.F. Momose INAA of Archaeological
Ceramic for Provenance Study. In: 3rd International Symposium on Nuclear Analytical Chemistry, Halifax, Canadá, June 11-14, 2001.
5. V.L. Mazzocchi, S.L. Baldochi, M.C.H.M. Ruiz,
C.B.R. Parente, C.O.Paiva-Santos, C.V. Santilli, K. Shimamura, T. Fukuda. Analysis by the
Rietiveld Method of Pure and Doped LiSrAlF6
and LiCaAlF6 Crystals at Different Temperatures. The Thirteenth International Conference
on Crystal Growth, em Kyoto, Japan, July 30
- August 4, 2001.
Reports
1. O.L. Gonçalez, R. Semmler, L.P. Geraldo. Desenvolvimento de medidas de seções de choque
fotonucleares obtidas com raios gama de captura de nêutrons térmicos. Relatório Técnico da
Faculdades SENAC de Ciências Exatas e Tecnologia - RT 10/2001.
6. A.C. Junqueira, R. Dogra, A.W. Carbonari,
R.N. Saxena, J. Mestnik- Filho, M. Moralles,
95
Measurements of quadrupole interactions in
LaMO3 (M = Cr, Fe, Co) perovskites by TDPAC. XII International Conference on Hyperfine Interactions, Park City, Utah, USA, August
12 to 17, 2001.
15. A.W. Carbonari, J. Mestnik filho, R.N. Saxena,
M.V. Lalic, H. Saitovitch, P.R.J. Silva, Hyperfine magnetic field investigation in CeIn3 Rare
Earths’ 2001 International Conference, Campos
do Jordão, Brazil, September 22 - 26, 2001.
7. A.W. Carbonari, J. Mestnik-Filho, R.N. Saxena, R. Dogra, J.A.H. Coaquira, Hyperfine interactions in CeT2 Ge2 (T = Mn, Fe, Co) heavy
fermion compounds measured by TDPAC. XII
International Conference on Hyperfine Interactions, Park City, Utah, USA, August 12 to 17,
2001.
16. L.C. Campos, C.B.R. Parente, V.L. Mazzocchi,
O. Helene "Determination of the β-Quartz Cell
Parameters using NMD Azimuthal Angular Differences". XIX Congress and General Assembly
of the International Union of Crystallography,
Geneva, Switzerland, august 2002.
8. L.G. Shpinkova, A.W.Carbonari, S.M.Nikitin,
J.Mestnik-Filho, Influence of electron capture
after-effects on the integrity of 111 In(111 Cd)DTPA complexes with organic ligands . XII
International Conference on Hyperfine Interactions, Park City, Utah, USA, August 12 to 17,
2001.
17. S.L.G. Petroni, M.A.F. Pires, C.S. Munita Use
of radiotracer in adsorption studies of copper on
peat. In: 7th International Conference on Nuclear Analytical Methods in the Life Sciences,
Antalya, Turquia, 16-21 June, 2002.. Book of
Abstracts, pg. 127, 2002
18. C.S. Munita, A. Nascimento, S.B. Schreiber, S.
Luna, P.M.S. Oliveira Chemical study of some
ceramics from Brazilian Northeast. In: 7th International Conference on Nuclear Analytical
Methods in the Life Sciences, Antalya, Turquia,
16-21 June, 2002. Book of Abstracts, pg. 196,
2002.
9. M. Olzon-Dionysio, S.D. de Souza, A.P. Ayala, A.W. Carbonari, E. Longo, Concentration dependence of the electric field gradient
in PbZr1−x Tix O3 ceramics. XII International
Conference on Hyperfine Interactions, Park
City, Utah, USA, August 12 to 17, 2001.
10. M.V. Lalic, J. Mestnik-Filho, A.W. Carbonari,
R.N. Saxena, H. Haas, Ab Initio calculations
of hyperfine interactions in CeIn3 . XII International Conference on Hyperfine Interactions,
Park City, Utah, USA, August 12 to 17, 2001.
19. I.B. Gonzaga, V.A. Maihara, F.M. Lajolo,
S.M.F. Cozzolino Evaluation of Selenium Contents in Diets of Pre-School children from the
Amazon Region in Brazil In: 11th International
Symposium on Trace Elements in Animals TEMA ( Berkeley, Califórnia, USA, 2-6 June,
2002.
11. L.G. Shpinkova, A.W. Carbonari, S.M. Nikitin,
J.Mestnik-Filho, Influence of electron capture
after-effects on the integrity of 111 In(111 Cd)DTPA complexes with organic ligands. XVI International Symposium on Nuclear Quadrupole
Interactions, Hiroshima, Japan, September 9 to
14, 2001.
20. V.L. da Silva, V.A. Maihara, M. Saiki, L.C.
Silva, S.M.F. Cozzolono Evaluation of nutritional status of Selenium in elderley women in
São Paulo/Brazil. In: 11th International Symposium on Trace Elements in Animals -TEMA
( Berkeley, Califórnia, USA, 2-6 June de 2002.
12. L.G.Shpinkova, A.W.Carbonari, S.M. Nikitin,
J.Mestnik-Filho, Are the electron capture aftereffects responsible for the fragmentation of
the 111 In(111 Cd)-complexes with organic ligands?
XVI International Symposium on
Nuclear Quadrupole Interactions, Hiroshima,
Japan, September 9 to 14, 2001.
21. V.A. Maihara, V.L. Silva, D.I.T. Fávaro, M.B.A. Vasconcellos, I.B. Gonzaga,
S.M.F.Cozzolino Daily Intake Selenium of
Selected Brazilian Population Groups In:
7th International Conference on Nuclear Analytical Methods in the Life Sciences – Antalya,
Turquia, 16-21 June, 2002 Book of Abstracts
pag:78.
13. L.G. Shpinkova, A.W. Carbonari, S.M. Nikitin,
J.Mestnik-Filho, EQI of 111 Cd in complexes
with 8-hydroxiquinolin and 8-mercaptoquinolin.
XVI International Symposium on Nuclear
Quadrupole Interactions, Hiroshima, Japan,
September 9 to 14, 2001.
22. V.A. Maihara, D.I.T. Fávaro, I.M. Sato, V.L.
Salvador, M.I. Rodrigues, M.B.A. Vasconcellos
Assessment of some mineral and trace elements
in workers diets from São Paulo Brazil, by Neutron Activation Analysis and X-Ray Fluorescence Techniques. In: 7th International Conference on Nuclear Analytical Methods in the Life
Sciences –Antalya, Turquia, 16-21 June, 2002.
Book of Abstracts pag. 222.
14. A.C. Junqueira, R. Dogra, R.N. Saxena, A.W.
Carbonari, J. Mestnik filho, M. Moralles, Hyperfine interaction study of LaMO3 (M = Cr,
Mn, Fe, Co) perovskite.
Rare Earths’ 2001
International Conference, Campos do Jordão,
Brazil, September 22 - 26, 2001.
96
23. M.B.A. Vasconcellos, Saiki, D.I.T. Fávaro, V.A.
Maihara, A.M.G. Figueiredo Neutron activation analysis at the research reactor center of
IPEN/CNEN-SP-biological and environmental
applications. In: 7th International Conference
on Nuclear Analytical Methods in the Life Sciences, Antalya, Turquia, 16-21 June 2002, Book
of Abstracts pag. 216.
31. G. Zanor, E.L. Piovano, D. Gairo, F.E. Larizzatti, D.I.T. Fávaro, S.R.D. Moreira Distribución temporal de elementos trazas em el registro sedimentario reciente de la Laguna Mar
Chiquita (Córdoba, Argentina). In : IX Reunião Argentina de Sedimentologia, Córdoba,
Argentina, 21-23 May 2002.
32. F. Galvan, E.L. Piovano, D. Gairo, F.E. Larizzatti, D.I.T. Fávaro, S.R.D. Moreira La procedencia del relleno seddimentario de la laguna
Mar Chiquita (Córdoba, Argentina). In : IX
Reunião Argentina de Sedimentologia, Córdoba, Argentina, 21-23 May 2002.
24. D.I.T. Fávaro, D. Mafra, V.A. Maihara, M.B.A.
Vasconcellos, S.M.F. Cozzolino Evaluation of
zinc and Fe in diets of patients with chronic
reanal failure. In: 7th International Conference
on Nuclear Analytical Methods in the Life Sciences, Antalya, Turquia, 16-21 June 2002, Book
of Abstracts pag. 39
33. M. Saiki, E.R. Alves, N.M. Sumita, P.H.N. Saldiva INAA applied to the study of Tradescantia
pallida plant for environmental pollution monitoring. In: 14th Radiochemical Conference,
Mariánské Lázne, Czech Republic, 14-19 April
2002. Book of Abstracts, pg. 143,
25. A.M.G. Figueiredo, A.L. Alcalá, M. Saiki, M.
Domigos The use of Tillandsia usneoides L.
as bioindicator of air pollution in São Paulo,
Brazil. 7th International Conference on Nuclear
Analytical Methods in the Life Sciences, 16-21
June 2002, Antalya, Turquia, Book of Abstracts
p. 161, 2002.
34. M. Saiki, S.O. rogero, I. Costa, E.R. Alves,
O.V. Correa, E. Dantas Analysis of metallic
biomaterials of medical interest and their corrosion products IN: 7th International Conference on Nuclear Analytical Methods in the Life
Sciences, Antalya, Turquia, 16-21 Jun e 2002.
Book of Abstracts, pg. 176
26. M. Ribeiro, D.I.T. Fávaro, R. Greiner, M.I.O.
Eiras, K.M. Baba, S.M.F. Cozzolino Concentrations of Zinc and Hexa and Pentaphosphate
Fractons in Brazilian Diets with Equilibrated
Macronutrient Contents. In: 11th International
Symposium on Trace Elements in AnimalsTEMA, Berkeley, Califórnia, USA, 2-6 June
2002.
35. N.M. Sumita, M. Saiki, P.H.N. Saldiva Analysis
of Tradescantia pallida plant exposed in different sites for biomonitoring purposes. IN: 7th
International Conference on Nuclear Analytical
Methods in the Life Sciences, Antalya, Turquia,
16-21 June 2002. Book of Abstracts, pg. 175
27. S.R.D. Moreira, D.I.T. Fávaro, F. Campanoli,
B.P. Mazzilli Sedimentation Rates and Metals
in Sediments from the Reservoir Rio Grande,
São Paulo, Brazil. In: 9th International Meeting on Environmental Radiochemical AnalysisERA 2002, Maidstone, Kent, U.K., 18-20 September de 2002.
36. M.K. Takata, M. Saiki INAA of cortical and
trabecular bone samples from animals. IN: 7th
International Conference on Nuclear Analytical
Methods in the Life Sciences, Antalya, Turquia,
16-21 June 2002. Book of Abstracts, pg 30
28. P.S.C. Silva, B.P. Mazzilli, D.I.T. Fávaro
Chemical and Radiological Characterisation of
Santos Estuary Sediments. In: 9th International Meeting on Environmental Radiochemical Analysis-ERA 2002, Maidstone, Kent, U.K.,
18-20 September 2002.
37. E.M. Adachi, M.N. Youssef, M. Saiki Application of the radiometric method for the evaluation of human dental loss caused by carbamide
peroxide bleaching agent. IN: 7th International
Conference on Nuclear Analytical Methods in
the Life Sciences, Antalya, Turquia, 16-21 June
2002. Book of Abstracts, pg. 203
29. S.R.D. Moreira, D.I.T. Fávaro, F. Campagnoli,
B.P. Mazzilli Tasa de Sedimentacion y Determinacion de Metales em Sedimentos del embalse
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38. M.J.A. Armelin, R.L. Ávila, R.M. Piasentin,
M. Saiki Chelated mineral supply effect evaluation on horses by Cu, Fe, K, Mn and Zn
determinations in their hair. IN: 7th International Conference on Nuclear Analytical Methods in the Life Sciences, Antalya, Turquia, 1621 June2002. Book of Abstracts, pg. 230
30. G. Zanor, F.E. Larizzatti, D.I.T. Fávaro, S.R.D.
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R.N. Saxena, H. Haas. "First-principles calculations of hyperfine fields in CeIn3 intermetallic
compound". XXV Encontro Nacional de Física
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"Nuclear methodology to perform clinical examination of urine". Congresso de Biociencias ,
3-7 September 2001 , Gramado , Brasil
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Likhachev, A.N. Gouveia, O.A.M. Helene, V.R.
Vanin, J. Mesa, E. Alves, F. Bringas, M.V.
Manso, J. W. Pereira-Filho, K. Shtejer, C.L.
Duarte, R. Semmler, C.B. Zamboni, S.A.C.
Jorge, G.W. Araújo, A. Miranda, O. Rodriguez,
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DNA por la radiación: propuesta de proyecto
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9. J.D.T. Arruda-Neto, C.B. Zamboni, C.L.
Duarte, R. Semmler, S.A. C.Jorge, G.W.
Araújo, K. Shtejer, A.N. Gouveia, A. Deppman,
O.A.M. Helene, V.R. Vanin, V.P. Likhachev,
M.V. Manso, A. Miranda, O. Rodriguez. "Effects of Gamma Radiation on the pBs-KS DNA
plasmid". XXIV Reunião de Trabalhos sobre
Física Nuclear no Brasil, 1-5 September 2001,
Águas de Lindóia, SP, p. 61
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of the structural and the electric field gradient
changes caused by the presence of Cd impurity
in delafossite CuAlO 2 compound." XXV Encontro Nacional de Física da Matéria Condensada. São Lourenço-MG, 15-19 May 2001.
10. M.V. Manso, A.N. Gouveia, A. Deppman, V.P.
Likhachev, O.A.M. Helene, V.R. Vanin, J.
Mesa, J.D.T. Arruda-Neto, C.B. Zamboni, M.
Saiki, G.P. Nogueira, A.C. Cestari, S.P. Camargo, O. Rodriguez, F. Guzman, F. Garcia.
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J.D.T. Arruda-Neto, C.B. Zamboni "The Concentration of Uranium in São Paulo Citizens’
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M.T.F. Cruz, J.Y.Z. Chávez. "Energy Levels in 149 Pm from the Decay of 149 Nd", XXIV
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Genezini, M.T.F. Cruz, J.Y.Z. Chávez, S.P. de
Camargo. Gamma Transitions from the BetaDecay of 193 Os” . XXIV Reunião de Trabalhos
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2001, Aguas de Lindoia, SP, p.16
26. C.S. Kira, V.A. Maihara Estudo comparativo
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18. I.M.M.A. Medeiros, C.B. Zamboni, F.A.
Genezini, L.C. Oliveira, J.A.G. Medeiros,
M.T.F. da Cruz, J.Y.Z. Chavez Energy Levels in 149 Pm from the decay of 149 Nd. XXIV
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27. V.A.Maihara, I.M. Sato, D.I.T. Fávaro, V.L.
Salvador, M.B.A. Vasconcellos Aplicação das
técnicas de Análise por Ativação com Nêutrons
e Fluorescência de Raios-X em Amostra de Fígado Bovino. In:VI Encontro Nacional de Aplicações Nucleares, ENAN, Rio de Janeiro, RJ,
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Arruda-Neto Desenvolvimento de metodologia
nuclear para o estudo das funções biológicas
de animais submetidos à ingestão de urânio.
XXIV Reunião de Trabalhos sobre Física Nuclear no Brasil, 1-5 September 2001, Aguas de
Lindoia, SP, p.16
28. C.S. Kira, V.A. Maihara, A.M.A. Sakuma Determinação Rápida de Minerais e Elementos
Traço em Amostras de Leite por Espectrometria de Emissão Atômica por Plasma de Argônio
Induzido (ICP-AES) In: VIII Encontro Nacional Sobre Contaminantes inorganicos - Symposio Sobre Essencialidade de Elementos na
Neutição Humana - Rio de Janeiro, RJ , 23-25
October 2002. Book of Abstract , pg. 75-76.
20. A.M.G. Figueiredo, M. Saiki, C.B. Zamboni,
F.A. Genezini Determination of trace elements
in Wistar rats bone by neutron activation
analysis. XXIV Reunião de Trabalhos sobre
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v.16, suplemento (2002) p. 251, ISSN 15177491.
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RJ , 23-25 October 2002. Book of Abstract pg.
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30. A.M.G. Figueiredo, A.L. Alcalá, M. Saiki, M.
Domingos Neutron activation analysis applied
to the study of Tillandsia usneoides as bioindicator of air pollution in São Paulo city. In: 25o
Reunião de Trabalho Sobre Fisica Nuclear no
Brasil, 31 August- 4 September., 2002, São Pedro, SP, p.54.
38. S.O. Rogero, M. Saiki, O.V. Correa, J.R.
Rogero, I. Costa Estudo de Corrosão de Aços
Inoxidáveis Utilizados como Biomateriais. In:
XV Congresso Brasileiro de Engenharia e Ciência dos Materiais, Natal, Rio grande do Norte,
09-13 November 2002. CD-ROM.
31. L.C. Oliveira, C.B. Zamboni, G.S. Zahn, M.A.
Maschio, A.M.G. Figueiredo, J.Y.Z. Cháves,
M.T.F. da Cruz The cadmium ratio technique
for studying biological functions of mammalians
submitted to uranium ingestion. In: 25o Reunião de Trabalho Sobre Fisica Nuclear no
Brasil, 31 August-4 September., 2002, São Pedro, SP, p.53.
39. L. C. Oliveira, C.B. Zamboni, G.S. Zahn, M.A.
Maschio, A.M.G. Figueiredo, J.Y. ZevallosChávez, M.T.F. Cruz, A.C. Cestari. ”The Cadmium Ratio Technique for Studying Biological Functions of Mammalian Submitted to Uranium Ingestion”. Reunião de Trabalhos sobre
Física Nuclear no Brasil, 31 August-04 September 2002, São Pedro, SP, p. 53.
40. J.Y. Zevallos-Chávez, M.T.F. da Cruz, M.N.
Martins, V.P. Likhachev, F.A. Genezini, C.B.
Zamboni. ”Monte Carlo study of secondary detection effects to improve the response function
for semiconductor detectors via the EGS4 code”.
Reunião de Trabalhos sobre Física Nuclear no
Brasil, 31 de agosto a 4 de setembro, São Pedro,
SP, p. 58 2002.
32. S.M.B. Oliveira, J.H. Larizzatti, D.I.T. Fávaro Comportamento do Mercúrio e outros
elementos-traço em Solos lateríticos da Província Aurífera do Tapajós. In : XLI Congresso
Brasileiro de Geologia - (João Pessoa, Paraíba,
Brasil, 15-20 September 2002).
33. P.S.C. Silva, G.W. Siqueira, B.P. Mazzilli, E.S.
Braga, D.I.T. Fávaro Determinação Elementar
nos Sedimentos do Estuário de Santos, São Vicente e baía de Snatos, São Paulo, Brasil. In:
Simposio Brasileiro de oceanografia OI/USP –
(São Paulo, Brasil, agosto de 2002).
41. I.M.M.A.
Medeiros,
J.A.G.
Medeiros,
C.B.Zamboni, R.O. Aguiar, L.D. Junior.
”Análise de Materiais Metálicos Odontológicos Utilizando Ativação Nuclear”. Reunião de
Trabalhos sobre Fí sica Nuclear no Brasil, 31
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34. C. Anjos, M. Saiki, R. Fulfaro Determinação de
elementos tóxicos presentes em materiais plásticos. In: Simpósio Internacional de Iniciação
Científica da USP, Campus da USP de São Carlos, São Carlos, 6-8 November 2002. CD- ROM.
42. J.W. Pereira Filho, J.D.T. Arruda-Neto, A.
Deppman, A. Gouveia, J. Mesa, R. Semmler,
C.B. Zamboni, M.V. Manso, F. Garcia, L.P.
Geraldo. "Design, construction and test of
an automatic fission tracks counter for interdisciplinary studies with the biomedical area".
Reunião de Trabalhos sobre Física Nuclear no
Brasil, 31 August-04 September 2002 , São Pedro, SP, p. 57
35. C. Pojar, M. Saiki, R. Fulfaro Caracterização de
biomateriais metálicos pelo método de ativação
com nêutrons. . In: Simpósio Internacional de
Iniciação Científica da USP, Campus da USP
de São Carlos, São Carlos, 6-8 November 2002.
CD- ROM.
43. G.S. Zahn, C.B. Zamboni, F.A. Genezini,
J.Y. Zevallos-Chávez, M.T.F. Cruz, H. Dias.
"Spectroscopy Investigation of Excited Levels in
193
Ir". Reunião de Trabalhos sobre Física Nuclear no Brasil, 31 August-04 September 2002 ,
São Pedro, SP, p. 36
36. E.M. Adachi, M.N. Youssef, M. Saiki, L.K.
Adachi Perda de massa dental com o uso do
peróxido de carbamida comparado ao condicionamento com ácido fosfórico. In: 19a .
Reunião Anual da Sociedade Brasileira de
Pesquisa Odontológica, Águas de Lindóia, SP,
31 August-04 September 2002. Pesquisa Odontológica Brasileira - Brazilian Oral Research,
v.16, supl. (2002) p. 242, ISSN 1517-7491.
44. M.T.F. da Cruz, J.Y. Zevallos-Chavéz, M.N.
Martins, V.P. Likhachev, F.A. Genezini, C.B.
Zamboni, S.P. Camargo. " 76 Se in the twoparticle vibration model - comparing configurations". Reunião de Trabalhos sobre Física Nuclear no Brasil, 31 August-04 September 2002,
São Pedro, SP, p. 39
37. L.K. Adachi, M. Saiki, T.N. Campos, E.M.
Adachi Avaliação in vitro do desgaste do esmalte dental humano por porcelans dentais. In:
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45. P. Perso, N. Added, R.M. Castro, M.T.F.
da Cruz, V.P. Likhachev, M.N. Martins,
J.C.O. Morel, E. do Nascimento, V.R. Vanin,
J.Y. Zevallos-Chávez, F.A. Genezini, J.A.G.
Medeiros, C.B. Zamboni, G.S. Zahn, E.B. Norman. "102 Rhm : a new limit for its cosmic ray
half-life". Reunião de Trabalhos sobre Física
Nuclear no Brasil, 31 August-04 September
2002, São Pedro, SP, p. 41
XXV Encontro Nacional de Física da Matéria
Condensada. Caxambú-MG, 7-11 May 2002
53. A.W. Carbonari, J. Mestnik-Filho, M.V. Lalic,
R.N. Saxena, J.A.H.Coaquira.
"Study of
the low temperature magnetic transitions of
the CeMn2 Ge2 compound by means of 140 Ce
TDPAC spectroscopy and first-principles electronic structure calculations". XXV Encontro Nacional de Física da Matéria Condensada.
Caxambú-MG, 7-11 May 2002.
46. J.D.T. Arruda-Neto, M.V. Manso Guevara,
V.R. Vanin, A. Deppman, V.P. Likhachev, J.
Mesa, O.A.M. Helene, M.N. Martins, A.C. Cestari, G.P. Nogueira, L.E.C. Fonseca, C.B. Zamboni, M. Saiki, A.N. Gouveia, S.A. C. Jorge,
O. Rodriguez, F. Guzmán, F. Garcia. "The
Role Played By Phytase And Metabolism In
The Accumulation Of Uranium In The Poultry
Bones". XX Reunião de Trabalhos sobre Física
Nuclear no Brasil,31 August-04 September 2002
, São Pedro, SP, pag 54
Workshops
47. F.A. Genezini, C.B. Zamboni, I.M.M.A.
Medeiros, M.T.F. da Cruz, J.Y. ZevallosChavéz, M.N. Martins, V.P. Likhachev, V.R.
Vanin, C.O. Guimarães-Filho, P.R. Pascholati.
"Directional Correlation of gamma in 155 Eu".
Reunião de Trabalhos sobre Física Nuclear no
Brasil, 31 August-04 September 2002 , São Pedro, SP, p. 40
1. J. Mestnik-Filho, M.V. Lalic, A.W. Carbonari,
R.N. Saxena. "Study of the low temperature
magnetic transitions of the CeMn 2 Ge 2 compound by means of 140 Ce TDPAC spectroscopy
and first-principles electronic structure calculations". WIEN2002 - WIEN2k Workshop @
PennState. Pensilvania State University, USA,
July 2b)25, 2002.
48. M.P. Raele, C.B. Zamboni, F.A. Genezini,
S.P. Camargo. "Análise Quali-Quantitativa
de Titânio Metálico de uso odontológico por
metodologia nuclear". Submetido: 2o Encontro
De Bioengenharia, São Carlos, 7-10 December,
2002.
2. J. Mestnik Filho."Viability study for the installation of a SANS beam-line at IPEN/CNENSP".Second Research Coordination Meeting
on "Development and Practical Utilization fo
Small Angle Neutron Scattering (SANS) Applications. IAEA Headquarters, Vienna, Austria,
August 20-23, 2002.
49. F. Brancaccio, M. S. Dias, M. F. Koskinas
"Automatic Control System for Measuring Currents Produced by Ionization Chambers". XXIV
Reunião de Trabalho sobre Física Nuclear no
Brasil, 1-5 September, 2001, Águas de Lindóia,
SP
3. R.N. Saxena, ”Basic safety features involved
in the operation of the IEA-R1 rearch reactor at IPEN”. Workshop on safety culture for
non-power nuclear installations (RLA/0/021),
Santigo, Chile, December 03-07, 2001.
50. C.B.R. Parente, V.L. Mazzocchi, Y.P. Mascarenhas. "O novo difratômetro de nêutrons do
IPEN-CNEN/SP". XV Congresso Brasileiro de
Engenharia e Ciência dos Materiais, Natal, RN,
November, 2002.
4. José Roberto Berretta, 2nd Workshop on Safety
and Regulation of Transportation and Storage
of Spent Fuel from Research Reactors (Regional
project RLA-4/018), Lima, Peru, October 2125, 2002.
51. L.C. Campos, C.B.R. Parente, V.L. Mazzocchi,
O. Helene. "Determination of the β-quartz cell
parameters using NMD azimuthal angular differences". XV Congresso Brasileiro de Engenharia e Ciência dos Materiais, Natal, RN, November 2002.
5. Roberto Frajndlich, Regional Workshop on
SCALE 4.4A II (IAEA-RLA/04/018) México
City, México, January 28-February 01, 2002.
52. M.V. Lalic, J. Mestnik Filho, A.W. Carbonari,
R.N. Saxena, M. Moralles. "Changes of the
electrical properties of CuAlO 2 delafossite under the doping with Cd: first-principles study".
6. Roberto Frajndlich, Regional Workshop on
SCALE 4.4A II (IAEA-RLA/04/018) Lima,
Peru, August 05-09, 2002.
101
7. Roberto Frajndlich, Spent Fuel Management for
the IEA-R1 Brazilian Research Reactor, First
Research Co-ordinated Meeting (RCM) on Corrosion of Research Reactor Aluminium Clad
Spent Fuel in Water (Phase II), Buenos Aires,
Argentina, October 28-November 01, 2002.
Safety of Research Reactors, AIEA, Viena, Austria, December 16-19, 2002.
9. Thadeu das Neves Conti Taller avanzado de
metodos de calculos y generacion de bibliotecas de datas para problemas especificos de reactores de investigacion, (RLA/9/046 ARCAL
LXVIII), Santiago, Chile, November, 2002.
8. Roberto Frajndlich, Code of Conduct on the
102
Academic Activities
Dissertations and Theses
"Automatic Control System for Measuring Currents
Produced by Ionization Chambers - Application in the
Standardization of 18 F and 153 Sm".
Thesis supervisor: M.S. Dias
Concluded in 2002.
M.Sc.
Concluded
Ilca Marli Moitinho Amaral de Medeiros
"Beta Decay Study of 149 Nd".
Thesis supervisor: C.B. Zamboni
Concluded in 2001.
Vanderlei Cardoso
"Methods for Curve Fitting Obtained by Means of
HPGe Spectrometers".
Thesis supervisor: M.S. Dias
Concluded in 2002.
Sheila Piorino Maria
"Estudo das características de distribuição de elementos terras raras em Solanum lycocarpum em
diferentes ambientes tropicais do Brasil por ativação
neutrônica".
Thesis Supervisor: A.M.G. Figueiredo
Concluded in 2001
Marcos Leandro Garcia Andrade
"Characterization of Several Converter Screens for
Neutron Radiography".
Thesis supervisor: R. Pugliesi
Concluded in 2002.
Eufemia Paez Soares
"Caracterização de componentes inorgânicos e tipos
de políimeros em materiais plásticos metalizados".
Thesis Supervisor: M. Saiki
Concluded in 2002
Mauro Noriaki Takeda
"Cascade Summing Correction for HPGe Spectrometers Calculated by Monte Carlo Method".
Thesis supervisor: M.S. Dias
Concluded in 2001.
Flávio Eduardo Larizzatti
"Determinação de Metais Pesados e outros elementos
de interesse por Ativação Neutrônica, em amostras
de sedimentos da Laguna Mar Chiquita (Córdoba,
Argentina)".
Thesis Supervisor: D.I.T. Fávaro
Concluded in 2002
Daniela Maria Bertero Coccaro.
"Estudo da determinação de elementos traço em
liquens para monitoração ambiental".
Thesis Supervisor: M. Saiki
Concluded in 2001
Amilton Reinaldo Aguiar
"Aplicação do método de análise por ativação com
nêutrons à detrminação de elementos traço em unhas
humanas".
Thesis Supervisor: M. Saiki
Concluded in 2001
Andreza Portella Ribeiro
"Determinação de metais pesados e outros elementos de interesse em sedimentos lacustres da estação
de tratamento de esgoto de Barueri, São Paulo, por
ativação neutrônica".
Thesis Supervisor: A.M.G. Figueiredo
Concluded in 2002
Ricardo Marcelo Piasentin
"Acompanhamento da variação mineral de duas
cultivares de Guandu (Cajanus cajan (L.) Millsp)
submetidas a diferentes doses de fertilizantes, pelo
método de análise por ativação com nêutrons".
Thesis Supervisor: M.J.A. Armelin
Concluded in 2001
Maríilia Grabriela Miranda Catharino
"Análise de mercúrio e selênio em materiais biológicos pelo método de análise por ativação com
nêutrons".
Thesis Supervisor: M.B.A. Vasconcellos
Concluded in 2002
Rosa Helena Peccinini Silva Rossi
"Utilização de Redes Neurais na Monitoração da
Potência do Reator IEA-R1".
Thesis Supervisor: A.J. Soares
Concluded in 2001
Edson Gonçalves Moreira
"Aplicação da análise por ativação com nêutrons ao
estudo da composição quíimica de materiais metálicos".
Thesis Supervisor: M.B.A. Vasconcellos
Concluded in 2002
Wilson de OLiveira Lavras
"Development of Activity Determination methods for
Radionuclides Used in Nuclear Medicine - Application in the Standardization of 51 Cr and 153 Sm".
Thesis supervisor: M.F. Koskinas
Concluded in 2002.
Carmen Silvia Kira
"Estudo da composição mineral e dos elementos traço
essenciais em amostras de leite e derivados por Espectrometria de Emissão com Plasma Induzido e Análise
por Ativação com Nêutrons".
Thesis Supervisor: V.A. Maihara
Franco Brancaccio
104
Concluded in 2002
Kátia A. Fonseca
"Development of Activity Determination by Coincidence Method of Mixed Decay (β − ,β + ,EC) Radionuclides - Application in the Standardization of 192 Ir,
152
Eu and 186 Re".
Thesis supervisor: M.F. Koskinas
Concluded in 2002
José Ricardo de Oliveira
"Programa Computacional para estudo da estratégia
de controle de um reator nuclear do tipo PWR".
Thesis Supervisor: A.J. Soares
Concluded in 2002
Luiz Carlos de Campos
"Parâmetros de Rede do Quartzo-β a 1003K determinados por Difração Múltipla de Nêutrons".
Thesis supervisor: C.B.R. Parente
Concluded in 2002
In Progress
Laura Cristina de Oliveira
"Desenvolvimento de Metodologia Nuclear para estudo das funções biológicas de animais submetidos à
ingestão de urânio".
Thesis supervisor: C.B. Zamboni
In Progress
Cláudia Regina Ponte Ponge-Ferreira
"Padronização de Radionuclíideos Beta Emissores
pelo Método do Traçador Utilizando Sistema de Coincidências ?????".
Thesis supervisor: Marina F. Koskinas
Astrogildo de Carvalho Junqueira
"Estudo de interações hiperfinas em óxidos perovskitas".
Thesis supervisor: A.W. Carbonari
Frederico Antonio Genezini
"Directional γγ Angular Correlation in
cleus".
Thesis supervisor: C.B. Zamboni
Fábio H. M. Cavalcante
"Study of the Magnetic Hyperfine Field in RAg compounds (R = rare earth)".
Thesis supervisor: A.W. Carbonari
Guilherme Soares Zahn
"Directional γγ Angular Correlation in
cleus".
Thesis supervisor: C.B. Zamboni
Marcelo Kazuo Takata
"Determinação in vitro de constituintes inorgânicos
em tecidos ósseos pelo metodo de analise por ativação
com nêutron".
Thesis Supervisor: M. Saiki
155
Sm Nu-
193
Os Nu-
Denise Simões Moreira
"Determination of X- and gamma ray emission probability per decay by means of Photon Spectrometers
and Coincidence Systems".
Thesis supervisor: M.F. Koskinas
Erion de Lima Benevenuti
"Metodologia para Monitoração e Diagnóstico da Vibração de Bombas Moto-Operadoras".
Thesis supervisor: D.K.S. Ting (CEN-IPEN)
Aída Maria Baccarelli
"Primary 4πβ-γ Coincidence System for the Standardization of Radionuclides Using Plastic Scintillators".
Thesis supervisor: M.S. Dias
Ph.D. Thesis
Concluded
Mauro Noriaki Takeda
"Simulation of 4πβ-γ Coincidence System for the
Standardization of Radionuclides by the Monte Carlo
Method".
Thesis supervisor: M.S. Dias
Cláudia C. Braga
"Application of Neural Network Technique to Neutron Spectrometry by Means of Bonner Spheres and
Activation Foils".
Thesis supervisor: M.S. Dias
Concluded in 2001
André L. Lapolli
"Study of hyperfine interactions of binary intermetallic systems".
Thesis supervisor: A.W. Carbonari
Eduardo Makoto Adachi
"Estudo in vitro da perda de massa dental humana
com o uso de agente clareador caseiro à base de
peróxido de carbamida a 10%, comparado ao condicionamneto com ácido fosfórico a 37%".
Co- orientador: M. Saiki
Thesis Supervisor: Micael Nicolau Youssef (Faculdade de Odontologia da USP) Concluded: 2001
Renato Semmler
"Medidas das Secções de Choque de Fotonêutrons do
9
Be, 13 C e 17 O com Radiação Gama de Captura de
Nêutrons Térmicos".
Thesis supervisor: A.W. Carbonari
105
Luciana Aparecida Farias
"Avaliação do conteúdo de mercúrio, metilmercúrio
e outros elementos de interesse em peixes, cabelos e
dietas de pré-escolares da região Amazônica".
Thesis Supervisor: D.I.T. Fávaro
A.W. Carbonari
TNA-5770 "Técnicas Nucleares Aplicadas à Investigação Microscópica de Materiais". - IPEN
C.B.R. Parente and V.L. Mazzochi
TNA-5769 "Aplicações da Difratometria de Nêutrons
no Estudo de Materiais". - IPEN
Claudia Petronilho Ribeiro Morcelli
"Elementos do grupo da platina (Pt, Pd e Rh) emitidos por conversores catalíiticos de automóveis e sua
distribuição em solos adjacentes a rodovias do Estado
de São Paulo".
Thesis Supervisor: A.M.G. Figueiredo
C.B.R. Parente and Vera Lúcia Mazzochi
TNA-5718 "Difração de Nêutrons". - IPEN
C.S. Munita
TNA - 5726 "Subestequiometria e Diluição Isotópica
em Análises Radioquímicas". - IPEN
Claudio Ailton Nogueira
"Distribuição de elementos metálicos em sedimentos
de drenagens do Parque Estadual da Ilha Anchieta,
SP".
Thesis Supervisor: A.M.G. Figueiredo
D.I.T. Fávaro and Ieda I.L. Cunha
TNA - 5717 "A Extração com Solventes Aplicada à
Química dos Produtos de Fissão". - IPEN
Antonio Lopez Alcalá
"Utilização de Tillandsia usneoides L. como bioindicadora da poluição aérea urbana da cidade de São
Paulo".
Thesis Supervisor: A.M.G. Figueiredo
L.P. Geraldo
TNA-5748 "Tópicos Especiais em Fissão Nuclear". IPEN
M.B.A. Vasconcellos and Mitiko Saiki
QFL 5766 "Radioquímica e Análise por ativação". USP
Andreza Portella Ribeiro
"Procedimentos de fracionamento quíimico comparados ao modelo de atenuação para a avaliação de
mobilidade de metais pesados em sedimentos da baia
de Sepetiba, Rio de Janeiro".
Thesis Supervisor: A.M.G. Figueiredo
M.S. Dias
TNA-5765 "Tópicos Especiais de Estatística Aplicada
à Tecnologia Nuclear". - IPEN
M.S. Dias and M.F. Koskinas
TNA-5733 "Tópicos Avançados de Medidas Nucleares". - IPEN
Marília Gabriela Miranda Catharino
"Biomonitoração de metais tóxicos em organismos
marinhos no Litoral Norte de São Paulo por análise
por ativação com nêutrons e espectrometria de absorção atômica".
Thesis Supervisor : M.B.A. Vasconcellos
R.N. Saxena
TNA-5727 "Tópicos Avançados em Química Nuclear". - IPEN
Thadeu das Neves Conti
"Aplicação do Método da Expansão em Funções
Hierárquicas na Solução das Equações de NavierStoques em duas Dimensões para fluidos compressiveis em alta velocidade".
Thesis Supervisor: E.L.L. Cabral. (Escola Politécnica da USP)
R. Pugliesi
TNA-5729 "Nêutrons Lentos. Aplicação na Tecnologia Nuclear e na Análise de Materiais". - IPEN
Courses offered
Short course
Post-Graduate courses (IPEN-USP)
A.J. Soares
TNR-5709 "Controle e Instrumentação de Usinas
Nucleares". - IPEN
C.B.R. Parente and V.L. Mazzochi
"Difração de Nêutrons e suas Aplicações".
During the I Simposio Brasileiro em Engenharia
Fisica (I-SBEF)
UFSCar, São Carlos, August 11 to 16, 2002.
V.G. Rodríguez, J.L.F. Bastos, D.A. de Andrade
TNR-5703 "Análise Termo - Fluido - Dinâmica de
Reatores Nucleares". - IPEN
A.M.G.G Figueiredo and J.M. Filho
TNA -5752 "Fundamentos de Tecnologia Nuclear". IPEN
Scientific Visits
106
ETE Carlos Chagas, São Paulo, SP
June 04, 2001.
M.S. Dias
National Institute of Standards and Technology
Gaithersburg, USA, October 2002.
M. Saiki
Uso de biomonitores no estudo da poluição ambiental
Companhia Siderúrgica de Tubarão, Vitoria, Espirito
Santo
July 13, 2001
M.F. Koskinas
CIEMAT - Centro de Investigationes Energéticas Mediambientales y Tecnológicas
Madrid, Spain, October 2002
D.I.T. Fávaro
Análise por Ativação Neutrônica : Teoria e Aplicações
Departamento de Química da Universidade Estadual
de Ponta Grossa, Ponta Grossa, Paraná
October 22, 2001
M.F. Koskinas
NPL- Nuclear Physical Laboratory
Teddington, UK, October 2002
W. Ricci Filho
Tennessee University, Nuclear Engineering Department, Knoxville, USA, May-August, 2001
Project for a Vibration Monitoring System on the
pump B of the Research Reactor IEA-R1 Primary Cooling System, IAEA Technical Project
(BRA/0/017)
R.N. Saxena
PAC spectroscopy: An important tool to investigate
the electronic properties of materials
Institute of Physics, University of São Paulo
October 13, 2002
Pos-doctoral fellows and visiting scientists
Seminars given by visiting scientists
Ronald Collé
National Institute of Standards and Technology, USA
September 16-27, 2002
Expert from IAEA on Nuclear Metrology
Ronald Collé
National Institute of Standards and Technology, USA
Activity Characterization of Brachytherapy Sources
Using Liquid Scintillation and Microcalorimetry
Techniques
September 24, 2002.
Milan V. Lalic
Institute of Nuclear Sciences "Vinca", Belgrade, Yugoslavia
Postdoctoral fellow- Since June 2000
Supported by fellowship from FAPESP
Research Grants
Project title: "Modernização dos Espectrômetros
para Realização de Pesquisa Básica e Aplicada Usando Técnicas Nucleares"
Project Coordinator: C.B. Zamboni
FAPESP, (1999-2001)
Peter De Regge
IAEA, Vienna, Austria
December, 2001
Expert from IAEA to audit the laboratories participating in the ARCAL XXVI IAEA Project according
to ISO/IEC17025:1999
Project title: "Standardizing Radionuclides in the
Nuclear Metrology Laboratory"
Project Coordinator: M.F. Koskinas
IAEA - BRA/02/14, (2001-2003)
Oscar Diaz Rizo
Institute for Nuclear Science and Technology, La Habana, Cuba
July, 2002
Supported by the IAEA Human resource development and nuclear technology support program
Project title: "Improvement of Neutron Radiography Facility
Project Coordinator: R. Pugliesi
IAEA- BRA/10/32, (1999-2001)
Project title: "perfeiçoamento das Condições de
Difratometria de Nêutrons no IPEN"
Project Coordinator: C.B.R. Parente.
FAPESP-95/05173-0, (1997-2003)
Seminars
Seminars given by staff members
Project title: "Aplicação de Raios X e Nêutrons
em Materiais Zeolíticos, Cerâmicos Ferroelétricos e
Solos Expansivos"
Project Coordinators: Y.P. Mascarenhas and V.L.
M. Saiki
Elementos tóxicos em materiais plásticos e sua reciclagem
107
Mazzocchi.
MCT/PADCT-RXENZCS, (2001-2003)
Project title: "Levantamento arqueológico da área de
confluência dos rios negros e Solimões: continuidade
das escavações, análise da composição química e montagem de um sistema de informações geográficas"
Project coordinators: E.G. Neves and C.S. Munita
FAPESP-002/02953-0, (2002-2003)
Project title: Viability study for the installation of a
SANS beam line at IPEN/CNEN-SP"
Project coordinator: J. Mestnik Filho
IAEA-11355/RO, (2001-2003)
Project title: "Quality Assurance in Analytical Laboratories"
Project Coordinator: M. Saiki
IAEA - ARCAL XXVI (RLA/4/ 013), (1997-2001)
Scientific collaborations
BIPM - Bureau International des Poids et Mesures,
Sèvres, France
CBPF - Centro Brasileiro de Pesquisas Fíisicas, Rio
de Janeiro, RJ
CEAOEN - Havana, Cuba
Centro de Investigaciones Geoquímicas y de Procesos
de Superfí icie, Universidad Nacional de Córdoba,
Córdoba, Argentina
Centro de Pesquisa de Pecuária do Sudeste - EMBRAPA, São Carlos, SP
Clínica Guilherme Paulo Deucher, São Paulo, SP
CTA - Centro Técnico Aeroespacial, S. J. dos Campos, SP
Departamento de Fisica Facultad de Ciencias Exatas
da Universidade Nacional de La PLata.
Departamento de Geociências da Universidade Federal do Amazonas
Departamento de Nutrição e Dietética da Faculdade
de Nutrição
da Universidade Federal Fluminense
Escola Politécnica da USP, São Paulo, SP
Escola SENAI Mario Amato de São Bernardo de
Campo, SP
Faculdade de Ciências Farmacêuticas da USP,
Riberão Preto, SP
Faculdade de Ciências Farmacêuticas da USP, São
Paulo, SP
Faculdade de Medicina da USP, São Paulo, SP
Faculdade de Odontologia da USP, São Paulo, SP
Faculdade de Odontologia da USP, Ribeirão Preto,
SP
Hahn-Meitner Institut, Berlin, Germany
INCOR/SP- Instituto do Coração da Faculdade de
Medicina da USP, São Paulo, SP
Institute of Nuclear Physics, Unversity of Moscow,
Russia
Instituto de Biociências da USP, São Paulo, SP
Instituto Nacional de Pesquisas da Amazônia (INPA)
Instituto Butantan, São Paulo, SP
Instituto de Física da USP, São Paulo, SP
Instituto de Pesquisas Tecnológicas do Estado de São
Paulo (IPT), São Paulo, SP
Instituto de Ciências Biomédicas (ICB), São Paulo,
SP
Instituto Superior de Ciências y Tecnologia Nucleares, Havana, Cuba
Instituto Tecnológico de Campinas (ITAL), Campinas, SP
Project title: "Validation and Application of plants
as biomonitors of trace element atmospheric pollution, analyzed by nuclear and related techniques"
Project Coordinator:M. Saiki
IAEA-CRP, (1997-2002)
Project title: "Estudo de interações hiperfinas magnéticas em sistemas intermetálicos de terras raras
com elétrons fortemente correlacionados"
Project Coordinator: A.W. Carbonari
FAPESP-2001/08577-8, (2001-2003)
Project title: "Estudo de interações hiperfinas eletromagnéticas em óxidos metálicos com estrutura tipo
perovskita"
Project Coordinator: R.N. Saxena
FAPESP-2002/-03771-3, (2002-2004)
Project title: "Aplicación de biomonitores y tecnicas nucleares relacionadas aplicadas a estudios de
contaminación atmosférica"
Project coordinator: M. Saiki
IAEA-ARCAL LX (RLA/7/010), (2002-2004)
Project title: "Implantação de um Sistema de garantia no Laboratório de Análise por Ativação Neutrônica do Centro do Reator de Pesquisas"
Project Coordinator:M. Saiki
FAPESP-02/00419-7, (2002-2004)
Project title: "Utilização de plantas bioacumuladoras
de metais para monitoramento biológico da poluição
urbana de São Paulo"
Project Coordinator: M. Saiki
FAPESP- 02/00418-0, (2002-2004).
Project title:"Chemical Metrology in Brazil"
Coordinator of the Section on Laboratories of High
Metrological
Competence: M.B.A Vasconcellos
CNPQ FVA/TIB 02/2002
Project title:"Estudo de dietas consumidas por trabalhadores de indústrias em relação aos seus constituintes nutricionais e contaminantes metálicos".
Project coordinator: V.A. Maihara
FAPESP-1999/12196-8, (2000-2002)
108
Sciences, ICENS, Jamaica
Internationales Hochschulinstitut Zittau, Zittau, Germany
ISCTN - Havana, Cuba
ISKP, University of Bonn, Bonn, Germany
II Physicalhes Institut, University of Göthingen, Germany
Kolynos do Brasil
Laboratoire d’Analyse par Activation Pierre Sue,
Centre dÉtudes Nucléaires de Saclay, France
Laboratório de Vidros da Faculdade de Tecnologia
de São Paulo
Laboratório Nacional de Metrologia das Radiações
Ionizantes (LNMRI), RJ
NIST - National Institute of Standards and Technology, Gaithersburg, USA
Núcleo de Estudos Arqueológicos da Universidade
Federal de Pernambuco
Michigan University-USA
Museu de Arqueologia e Etnologia da USP, São Paulo,
SP
Paul Scherrer Institut-PSI-Switzerland
Universidade Santo Amaro - UNISA
Universidade Católica de Santos
Instituto Adolfo Lutz (IAL) , São Paulo, SP
Instituto de Geociências da Universidade de Campinas, Campinas, SP
Instituto de Geociências da USP, São Paulo, SP
Instituto de Geociências da Universidade do Rio
Grande do Sul, Porto Alegre, RS
Instituto de Geociências da Universidade de Brasília,
Brasília, DF
Instituto de Física da Universidade Federal de Sergipe
Instituto Astronômico e Geofísico da USP, São Paulo,
SP
Instituto Oceanográfico da USP, São Paulo, SP
Instrumentation Associates Inc., Missouri, EUA
Instituto de Física da USP, São Carlos, SP
Instituto de Física da UNICAMP, Campinas SP
Instituto de Química da UNESP, Araraquara, SP
Instituto de Física da Universidade Federal de Feira
de Santana, Ba
Instituto de Fí isica da Universidade Federal de São
Carlos, SP
Instituto de Botânica, São Paulo, SP
Instituto Nacional de Pesquisas da Amazônia (INPA)
Interfaculty Reactor Institute, Delft University, Delft,
Netherlands
International Centre for Environmental and Nuclear
109
Services
Routine services offered by the Center
the same sample it is possible to determine about 20
to 30 elements. The results of the chemical elements
analysis are reported as µg/g or µg/kg depending on
the kind of sample analyzed and on the concentration levels. Generally at least two determinations are
made for each sample and the delivery time of the
analysis range from one to four weeks, depending on
the half- lives of the radioisotopes being measured.
About 3700 samples were analyzed by the neutron
activation method during 2000-2002. The CRPq research staff used a large part of these analyses for
their own research work. Other samples were analyzed as a part of the routine service offered to other
departments of IPEN, different research institutions,
universities and industries. Elements, like Ag, As,
Au, Ba, Br, Cr, Ca, Cs, Co, Cr, Fe, Hg, Hf, K,
Mn, Na, Nb, Sb, Se, Sc, Zn, rare earths, U, Th, Ta,
W among others were determined in several different
kinds of samples, such as: mineral supplements, sulfuric acid solutions, thorium oxide, topaz, steel and
other alloys, geological samples, air filters, zirconium
oxides, plastics, fish samples.
About 100 neutron radiographs were taken for
non-destructive analysis of different types of objects
using the neutrongraphy facility installed in the reactor. Many of these neutron radiography experiments
were realized for the development of real-time NR
method recently implemented at the IEA-R1 research
reactor. Several other objects were radiographed as
a part of the service to external users. Centro Técnico Aerospacial (CTA) and Embraer were the main
users of this service. The Nuclear Metrology Laboratory (LMN) produced about 130 calibrated radioactive sources included among these 57 Co, 60 Co, 131 I,
133
Ba, 137 Cs, 152 Eu and 241 Am. Whereas a large part
of these sources were supplied to external users like
medical clinics, hospitals, universities, and research
laboratories, some were supplied to the research laboratories within IPEN. More than 230 neutron flux
measurements (both thermal and epithermal neutrons) were carried out in different positions of the
reactor core, most of them on request from the reactor operation staff. This service was also used by
some of the research groups of CRPq. The neutron
flux measurements were carried out by using the gold
foil activation technique.
During the period 2001-2002, about 3000 capsules
containing various types of samples were irradiated
with neutrons in the reactor. While about 1800 standard aluminum capsules, each containing between 1
and 15 samples were irradiated at different positions
in the reactor core, accessible through the pool, other
samples were irradiated through fast pneumatic irradiation facilities, using special polyethylene capsules
(rabbits). The samples requiring short irradiation
times (few seconds to several minuets) are usually
irradiated through the pneumatic facilities. External users like Radiofarmaceuticals Center at IPEN,
other research institutions and universities usually
require samples to be irradiated in the core where
much higher neutron fluxes are available. The resulting radioactive isotopes are used in nuclear medicine,
research and different industrial applications. The
principal user of the pneumatic irradiation facilities
is CRPq it self, where mostly the samples for neutron
activation analysis are irradiated.
Neutron activation analysis is one of the most relevant applications of nuclear research reactors. Due
to the high neutron fluxes available in these reactors,
it is possible to analyze a large part of the elements of
the periodic table with good sensitivity, precision and
accuracy. In most applications, the method used is instrumental neutron activation analysis, INAA, which
consists in submitting the samples to be analyzed to
a neutron flux and measuring the induced radioactivity in a gamma-ray spectrometer. Instrumental neutron activation analysis is a versatile method, which
can be applied to a wide range of sample matrixes,
such as biological (hair, nails, bones and tissues in
general), geological (rocks, soils, ores), environmental (aerosols, rainwater, sediments), metallic (metals
or alloys), archaeological (pottery, coins), industrial
(plastics, foams, resins) and many others. The elements that are generally favorable for INAA are: Na,
Mg, Al, Cl, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Cu,
Zn, Ga, As, Se, Br, Rb, Zr, Nb, Mo, Pb, Ag, Cd, Sb,
Cs, Ba, La, Hf, Ta, W, Ir, Pt, Au, Hg, Ce, Nd, Sm,
Eu, Gd, Tb, Yb, Lu, Th, U. By using a suitable combination of irradiation, delay and measuring times, it
is possible to make multi-elemental analysis, i.e., in
111
Personnel
Research staff
Reactor Staff
Adalberto J. Soares
Ana M.G. Figueiredo
Artur W. Carbonari
Carlos B.R. Parente
Casimiro J.S. Munita
Cibele B. Zamboni
Déborah I.T. Favaro
Guilherme S. Zahn
José Mestnik- Filho
Maria J.A. Armelin
Marina B.A. Vasconcellos
Marina F. Koskinas
Mário O. de Menezes
Maurício Moralles
Mauro S. Dias
Mitiko Saiki
Rajendra N. Saxena
Renato Semmler
Reynaldo Pugliesi
Rosemeire P. Paiva
Valdomir. G. Rodrigues
Vera A. Maihara
Vera L. Mazzocchi
Operators
Alberto J. Fernando
Antonio C. A. Vaz
Antonio C. I. Rodríguez
Antonio G. Sara Neto
Antonio L. Pires
Carlos A. Loyola
Carlos S. Nohara
Edison S. Longo
Eduardo G. Araujo
Italo Salzano Jr.
Jose R. Berretta
Jose R. de Mello
Julio B. M. Tondin
Omar C. Félix
Osvaldo G. Fernández
Roberto Franjdlich
Sidney P. de Souza
Toni Carlos C. de Lima
Walter Ricci Filho
senior operator
senior operator
senior operator
senior operator
trainee
senior operator
trainee
trainee
senior operator
senior operator
Maintenace staff
Technologists
Algeny V. Leite
Arvelindo Semensati
Emanoel N. B. dos Santos
Erion L. Benvenuti
Gilson F. Maciel
Hélio T. Massaki
José P. N. Cardenas
Marcos R. de Carvalho
Marcos Yovanovich
Mauro O. Martins
Rubens V. F. da Silva
Shigeo Yokoyama
Adolfo Marra Neto
Cláudio Domienikan
Edson G. Moreira
Franco Brancaccio
Ione M. Yamazaki
Ricardo M. Piasentin
Thadeu N. Conti
Technicians
Edson R. Alves
Fábio de Toledo
Maurício Marques
Onofre Alves de Almeida
Paulo Sergio Santiago
Regina B. Ticianelli
Roberto M. Schouri
electronic
mechanical
mechanical
electrical
computer
electronic
mechanical
mechanical
mechanical
mechanical
Resident Heath Physics Staff
Carlos A. da Costa
Cláudio M. Constâcio
Eduardo W. M. Santos
Eduardo Y. Toyoda
Flávio L. Rossatto
Haroldo R. da Silva
Ricardo B. Lemes
Ricardo N. de Carvalho
Sérgio M. Vaz
Sidnei de Lima
Valdir M. Lopes
Vicente Rodrigues Jr.
Secretaries
Irene C. dos Santos
Marina J. N. Mello
Quality System Manager
Research Collaborators
Tereza C. Salvetti
113
supervisor
supervisor
supervisor
supervisor
Ana C. Cestari
José A.G. de Medeiros
Juan Y.Z. Chávez
Katherin S. Diaz
Leonardo Dalaqua Jr.
Luiz Paulo Geraldo
Manuel T.F. da Cruz
Maria V. M. Guevara
Nora L. Maidana
Roberta N. Attili
Sonia P de Camargo
Vladimir P. Likhachev
Willi Pendl Jr.
IFUSP
UNISA
IFUSP
IFUSP
PROMON
UNISANTOS
IFUSP
IFUSP
IFUSP/LOS ALAMOS
INST. TEC. MAUA
UNISA
IFUSP
UNICID
Graduate students
Ph.D.
Aida M. Baccarelli
Astrogildo C. Junqueira
Claudia C. Braga
Claudia P.R. Morcelli
Denise Simões
Frederico A. genezini
Katia A. Fonseca
Luis C. Campos
Roberto T. Saito
Scholarship
FAPESP
CNPq
FAPESP
CNPq
CNPq
CNPq
Scholarship
Andreza P. Ribeiro
Amilton R. Aguiar
Carmen S. Kira
Daniela M.B. Coccaro
Edson G. Moreira
Eufemia P. Soarez
Fábio H. M. Cavalcante
Flávio E. Larizzatti
Ilka M.M. Amaral
José Ricardo de Oliveira
Laura C. de Oliveira
Lena A. Katekawa
Marcelo K. Takata
Marília G. M. Catharino
Mauro N. Takeda
Roberto T. Saito
Rosa Helena P.S. Rossi
Sandra F. Mateus
Sheila Piorino Maria
Vanderlei Cardoso
Wilson O. Lavras
FAPESP
CNPq
Scholarship
Adriana M. Kamiya
Alessandra Fuga
Alexandre G. de Melo
André K. Tavaraya
Catarina N. de Oliveira
Daniela T. Nardi
Décio H. Nomura
Érika F. Momose
Juliana R. de Brito
Kelly C. Zangrande
Lídia K. Horimoto
Marcelo Bernardes Garcia
Márcio I. Rodriguez
Maria A.R. Silveira
Maria I.O. Eiras
Murilo C. da Silva
Patricia Y. Matsubara
Sami S.A. Lopes
Simone Avino
Vanessa A. de Campos
Vanessa N. da Silva
Yuki C. Negihora
CNPq-PIBIC
Student Trainees
CNPq
M.Sc.
Undergradute Students
Eduardo M. Adachi
Marco A. Maschio
Rodrigo O. Aguiar
Silvia H.A. Nicolai
CNPq
CNPq
CNPq
FAPESP
FAPESP
CNPq
CNPq
CNPq
FAPESP
114
CNPq-PIBIC
CNPq-PIBIC
FAPESP
FAPESP
FAPESP
CNPq-PIBIC
CNPq-PIBIC
CNPq-PIBIC
CNPq-PIBIC
CNPq-PIBIC
CNPq-PIBIC