Research in Nuclear Engineering at Penn State University

Research in Nuclear Engineering at
Penn State University
Arthur T. Motta
Chair of Nuclear Engineering Program
Department of Mechanical and Nuclear Engineering
and Materials Science and Engineering
The Pennsylvania State University
[email protected]
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[email protected]
Minha trajetoria pessoal
• UFRJ Engenharia Mecanica – opcao nuclear
• Mestrado na COPPE Engenharia Nuclear, tese em
Termohidraulica
• Doutorado University of California, Berkeley, Materials
• Pos doutorado na Franca, Centro de Estudos Nucleares de
Grenoble
• Pos doutorado no Canada, Chalk River Laboratories
• Professor at Penn State, Nuclear Engineering desde 1992,
chefe de programa 2010.
Outline
• Review of Penn State University
• Research in Nuclear Engineering at Penn State
• Why graduate study? How to get there
Review of Penn State
Penn State University
• Located in State College, PA
• About 45,000 students on
campus, 80,000 overall,
research university
• College of Engineering has
almost 300 professors, 13 +
programs
• Population about 80,000
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Views of Campus and Town
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Some numbers
• Undergraduate Program in Nuclear Engineering enrollment
has been increasing dramatically (highest number in US).
Currently about over 200 students in program, 75 graduated
last year
• Nuclear Engineering Graduate Program has 50 + resident
students (about 60% PhD) and over 100 distance education
students (M.Eng.)
• Research funding de $500,000/ per faculty member/year on
the average
Nuclear B.S. Degrees Granted
Comparison with peers (UG graduation)
Mechanical and Nuclear Engineering
at Penn State
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Department of Mechanical and Nuclear Engineering offers PhD
programs in ME and NucE. Nuclear Engineering research areas
– Reactor Physics and Fuel Management (Profs. Ivanov, Watson
and Avramova)
– Reactor Thermal Hydraulics (Profs. Kim and Cheung)
– Nuclear Materials (Profs. Motta and Catchen)
– Nuclear Science Applications (Profs. Jovanovic and Brenizer)
– Neutron Beam Analysis (Prof. Unlu)
– Reactor Controls (Prof. Ray)
– Nuclear Fuel Cycle (Prof. Fratoni)
– Radiochemistry (Dr. Johnsen)
12 professors, 50 + graduate students
MNE had more than 25 million dollars of research expenditures
while Penn state overall had 780 million dollars 2009-2010
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THE ADVANCED MULTI-PHASE FLOW
LABORATORY (AMFL)
Prof. Seungjin Kim
Design and perform experiments and theoretical and
computational analysis on various multi-phase flow
phenomena found in nuclear reactor systems.
http://www2.mne.psu.edu/amfl/
.
The Advanced Multi-phase Flow Laboratory, Department of Mechanical and Nuclear Engineering
Tel: (814) 867-0282 Email: [email protected]
FLOW VISUALIZATION
Bubbly flow: jf = 5.00, jg,atm = 0.10 m/s
Slug flow: jf = 1.00, jg,atm = 1.64 m/s
Plug Flow: jf = 1.00, jg,atm = 0.16 m/s
TWO-PHASE FLOW TRANSPORT IN COMBINATORIAL CHANNELS
Sponsored by U.S. DOE - NEER Program; Continued by U.S. NRC
To study two-phase flow transport under the effects of
geometric restrictions and orientations
L/D=177
L/D=1.5
L/D=93
L/D=15
L/D=3
L/D=61.5
L/D=66
49.5
L/D=3
L/D=34.5
• 5.08 cm ID acrylic test section
25.5
L/D=87
L/D=7.5
1.5
L/D=165
• Glass elbows
• Development length
Vertical: ~ 60D or ~3 m
Horizontal: ~180 or ~9 m
• Two inlet conditions
P4; (L/D)H = 3
P5; (L/D)H = 30
P7; (L/D)H = 93
P10; (L/D)H = 177
P3; (L/D)V = 62
P11; (L/D)V = 1.5
P12; (L/D)V = 15
P3; (L/D)V = 60
P11; (L/D)V = 1.5
Measured Void Fraction Profiles
jf=3.0 m/s & jg=0.35 m/s
P12; (L/D)V = 16.5
TRACE CODE DEVLEOPMNET USING
INTERFACIAL AREA TRANSPORT EQUATION
Sponsored by U.S. NRC
To develop TRACE code capable of dynamic modeling of two-phase flow using the
interfacial area transport equation
• Dynamic prediction throughout regime
transition
Vertical Downward Air-Water
Pipe Size: 2.54 cm ID
jg,loc,1= 0.453 m/s, jf= 3.110 m/s
• Eliminates bifurcation / numerical
oscillation
• Significant improvements in code
prediction results
Error bars shown: ±20%
HORIZONTAL TWO-PHASE FLOW
Sponsored by Bettis Atomic Laboratory
To establish database for CMFD code development at Bettis Atomic Power
Laboratory
• 38.1 mm ID acrylic test section
• Adiabatic air-water
• L/D ~ 250 or 9.5 m
• Capable of comprehensive twophase flow regimes
The Advanced Multi-phase Flow Laboratory, Department of Mechanical and Nuclear Engineering
Tel: (814) 867-0282 Email: [email protected]
Igor Jovanovic
Associate Professor of Nuclear Engineering
Current projects:
•laser particle acceleration in plasma waveguides
and dielectric photonic bandgap structures
•laser-induced breakdown spectroscopy for
nuclear forensics
•quantum sensors for super-resolution in imaging
•graphene-based radiation detectors
•coherent neutrino-nucleus scattering
•directional neutron detection
•expect to hire 1-2 Ph.D-track students next year
See http://www.mne.psu.edu/IJ for more info
Department of Mechanical and Nuclear Engineering & Radiation Science and Engineering Center
Radiation Science and Engineering Center
Breazeale Nuclear Research Reactor
1 MW TRIGA
3x1013 n/cm2 sec thermal neutron
flux at core center
Gamma Irradiation Facilities
In-Pool irradiators
Gamma Cell 220 Dry Irradiator
(12,000 Curie Co-60, 1.5 MRads/hour)
Hot Cells
Radiation Detection and Measurement Labs
Neutron Beam Laboratory
Radionuclear Applications Laboratory
Radiochemistry Laboratory
Department of Mechanical and Nuclear Engineering & Radiation Science and Engineering Center
Measurements of signature trace elements in
dated tree ring samples to make correlations
with environmental effects
Using Neutron
Activation Analysis
and Compton
Suppression
System at RSEC
Dendrochemistry
measurements are
being performed
for thousands of
dated tree ring
samples for
identifications of
volcanic eruptions
and climate effects
in history.
Department of Mechanical and Nuclear Engineering & Radiation Science and Engineering Center
Analysis of spent fuel samples with Compton
Suppression System at RSEC
Gamma spectroscopy
spent fuel samples to
determine isotopic
content
Department of Mechanical and Nuclear Engineering & Radiation Science and Engineering Center
Development of innovative radioactive isotope
production techniques at RSEC
Radioisotope
production 41Ar,
56Mn, 82Br and 24Na
is being explored at
RSEC. Production of
67Cu and by
extension 64Cu to
alleviate the national
shortage of needed
isotopes.
Department of Mechanical and Nuclear Engineering & Radiation Science and Engineering Center
New Radiochemistry Teaching Laboratory
Current Research
Bill Cheung – Professor of Mechanical & Nuclear Engineering
Project #1: Study the effects of spacer grids on heat transfer.
Sponsors: US Nuclear Regulatory Commission, Purdue Univ. Thermal
Hydraulics Institute
Project #2: Conceptual design of core catcher in case of core accident
for severe accident mitigation for Eu-APR1400
Sponsors: Korean Atomic Energy Research Institute
SPACER-GRID THERMAL-HYDRAULICS (SGTH)
Sponsored by U.S. NRC
To study spacer-grid effects on the cooling of PWR fuel assemblies, including
the oscillating reflood conditions
• Reference System: 17x17
Westinghouse PWR
steam
separator
• 7x7 full length heated rod
bundle assembly
Pressure oscillation
damping tank
exhaust
muffler
upper
plenum
Clad Temperatures at Constant Reflood Rates
2.54 cm/s (Run #5092) vs. 5.08 cm/s (Run #5086)
1800
heated water
supply tank
T em p eratu re (˚F )
1400
test section: 7x7
rod-bundle flow
housing
1000
Exp 5092 D3 2.69 m (106")
600
Exp 5092 D3 2.80 m (110")
Exp 5086 D3 2.69 m (106")
lower
plenum
Exp 5086 D3 2.80 m (110")
200
0
100
200
300
Time (sec)
400
500
Reactor Dynamics and Fuel Management Group
Reactor Dynamics and Fuel Management Group (RDFMG) – research
group consisting of 18 graduate students and four faculty:
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Dr. K. Ivanov – Distinguished Professor of NE, Director
Dr. M. Avramova – Assistant Professor of NE, Associate Director
Dr. J. Watson – ARL
Dr. S. Levine – Professor Emeritus of NE
Established in 1999 and since then has graduated students with the
following Nuclear Engineering (NE) degrees - 21 PhD, 33 MS, 19 ME,
and 5 BS with Honors
Advanced Coupled Neutronics and Thermal-Hydraulics Methodologies
for Integrated Fuel Management and Safety Analysis
www.mne.psu.edu/rdfmg
Hydrogen from corrosion responds to temperature
and stress gradients (=> hydride distribution not
homogeneous)
Radial re-distribution due to heat flux induced temperature
gradient => hydride rim
Oxide thickness differences; when oxide spalling occurs,
hydride blisters can form
Other changes due to localized corrosion or crud deposition
Concentration in liner
Axial profile due to corrosion differences from coolant
temperature, grid spacers and inter-pellet region
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Azimuthal profile because ofµmdifferences in flux and in cooling
around the clad circumference
Miyashita 2007, Tsai & Billone 2002, Pyecha 1985
November 2011
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The project is based on the coupling of four
simulation codes and a hydride model
Cross-section library
Off-line coupling CFD
Burn-up
Cobra-TF
(Thermohydraulic)
FRAPCON
Local
Power
DeCART
(Neutronic)
Local
Power
[H]
Local
bulk T
Boundary
conditions
Cross
sections
FRAPTRAN
σ (r,θ,z)
T (r,θ,z)
[H] (r, θ,z)
At a given burn up
Hydride model
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Hydride
distribution(r,θ,z)
Reactor Core Designs
Investigate two reactor core
designs representative of current
PWRs and BWRs.
As a BWR representative we will
utilize the General Electric BWR-4
design with 24-month cycle
based on Peach Bottom 2 plant.
Typical PWR 18-Month Loading Pattern
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Consider as PWR representative
a typical Westinghouse 4-loop
pressurized water reactor core
design with a 18-month highburnup cycle
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Assembly Type 1
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Assembly Type 3
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PB-2 BWR Loading Pattern
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Multi-Physics Analysis
Core cycle calculations will be performed with CASMO-4/SIMULATE-3
Based on these results representative core and pin locations exhibiting
strong azimuthal flux and temperature gradients will be identified
Advanced high-fidelity multi-physics modeling capability will be utilized
for “zoom-in” snapshot calculations of the identified locations
Local power / linear heat rate
DeCart/TORTTD
Local
power
CTF
Local bulk temperature & density
Local pressure
Local bulk temperature
Local surface HTC
Local flow area
reduction
Heat transfer to coolant
Initial flow area
reduction
Local fuel
temperature
FRAPTRAN
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Initial fuel state
FRAPCON
Multi-physics high-fidelity simulation framework
Calculation Sequence
Selection of Core
locations for two
prototypical reactors
using CASMO4/SIMULATE-3
Pteparation of
Multi-group PinCell CrossSection Library
DeCart/TORT
calculation of
Φn
CTF calculation of
mass flow rate, T
in coolant
CTF sub-pin analysis capability for flexible
azimuthal modeling of flux and temperature
distributions
Calculation of T(r,θ,z) by
FRAPTRAN
Flowchart of Calculation Tasks
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Azimuthal flux distribution in a pin-cell of
assembly with intra-assembly flux gradient
Coupling of Core Thermal-Hydraulic Models with
other Models and Phenomena
Faculty Participants: Prof. Avramova
Lab/Center Name: RDFMG
Sponsor: AREVA NP, MHI, NECSA and GRS
MCNP/NEM/CTF –
Accelerated Monte
Carlo Calculations with
Thermal-Hydraulic
Feedback
Multi-Scale MultiPhysics System
NEM/CTF/FRAPCON
TORT-TD/CTF coupling
for High-Fidelity
Calculations
RELAP-3D/COBRATFCoupling for LOCA
Analysis
Coupled 3-D Neutronics/Thermal-Hydraulic
System Safety Analysis
Faculty Participants: Dr. Watson, Prof. Ivanov and Prof. Avramova
Lab/Center Name: RDFMG
Sponsor: US NRC, GSE, Risk Engineering Ltd., ARL
Fully implicit
coupling of
TRACE and
PARCS
Cross-section
modeling for
transient
applications
Real –time
simulators for
operator training
Research interests
Nuclear reactor design
– Accident tolerant fuel for light
water reactors
– Liquid fuel thorium reactors
– Critical and subcritical systems
for actinides transmutation
Nuclear fuel cycle and system analysis
– Thermal modeling of repository
– Energy return over investment
Massimiliano Fratoni
Assistant Professor of
Nuclear Engineering
[email protected]
Microencapsulated
Metallic Matrix (M3) fuel
Scope: design light water reactors
to operate with M3 fuel
Motivations: M3 fuel is expected
to improve fuel performance
and reactor safety; M3 fuel
does not require cladding and
eliminates all failure
mechanisms associated with
cladding
Sponsors and collaborators:
– Oak Ridge National
Laboratory
Zr-Alloy
Matrix
Zircaloy
Cladding
Coated
Fuel
Particle
UO2
Pellet
Gap
Conventional LWR
UO2 Fuel Rod
Integral LWR
M3 Fuel Rod
M3 fuel consists of TRISO particles
dispersed in a zirconium matrix
Microencapsulated
Metallic Matrix (M3) fuel
Challenge: heavy metal load in M3 fuel is
50% or less than in standard fuel
Approach:
– High fidelity neutronics
modeling using stochastic
codes (Serpent, MCNP)
– Single assembly and full core
models
Current design requirements:
– High density fuel
– 15% enrichment
– Small rod pitch-to-diameter
ratio (1.10)
– Distributed neutron poison
(BN) to compensate reactivity
excess
M3 fuel compared to standard fuel
requires higher enrichment and larger
fuel rods
Generic repository
thermal modeling
Scope: Develop and implement a simplified thermal
modeling tool for generic (no site and no media
specific) waste repository
Motivations: thermal limits determine the waste
management strategy (surface storage duration,
waste package size, repository capacity, etc.);
necessity to analyze and compare numerous options
Sponsors and collaborators:
– DOE
– Lawrence Livermore
Nat. Lab.
Generic repository
thermal modeling
An analytical model was
developed for scoping natural
or engineered barriers peak
temperature
Peak temperatures were
compared against thermal
limits
Combinations of three media
(granite, clay, and salt) and six
fuel forms derived from three
fuel cycle options (oncethrough, modified open, and
closed) were analyzed
Result example: large waste packages
are preferred for transportation but
they could require long surface storage
Razoes para se fazer pos graduacao
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Aprofundar conhecimentos
Fazer pesquisa
Aumentar sua marketabilidade
Mais $$$
~$10,000/yr
Source:
www.asme.org
2011 salary survey
Graduate Student Life
• Graduate students are generally supported through their degree program as a
Graduate Teaching Assistant or Graduate Research Assistant. The stipend for
an incoming MS student is $1900 / month.
• With an Assistantship, your tuition and health coverage are paid for through the
department (for TA) or through the research grant (for RA)
• The MS degree generally requires two years while the PhD degree requires a
total of 4-5 years both of which depends on many factors
Pos-graduacao em Eng. Nuclear
PhD: doutorado, leva de 4 a 5 anos, precisa exame
de candidatura (coisas basicas da nuclear), exame
compreensivo (projeto de tese) e defesa final.
MSc: grau de pesquisa, 2 anos, 24 creditos de
cursos, e tese (financiado por projetos de pesquisa.
M.Eng: grau profissional, 2 anos, baseado em
cursos (financiado pelo aluno).
Como chegar la? Pos graduacao
• Bolsa de doutorado pleno CNPq ou CAPES
• Bolsa sanduiche, dado pelos mesmos orgaos
• Financiamento pela universidade americana
O que e necessario?
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Aplicacao: mne.engr.psu.edu (tem uma taxa)
Curriculo escolar traduzido
Graduate Record Examination (treinar)
TOEFL (test of English as a Foreign Language)
Cartas de recomendacao (2 ou 3 dadas por
professores que os conhecam)
• Personal essay (dizendo sua motivacao, interesse,
eventualmente areas de foco, etc)
Suporte americano
• Bolsa mensal
• Ensino pago (ensino americano nao e gratis,
mas a bolsa cobre)
• Seguro de saude
• Pode ser research assistantship ou teaching
assistantship (monitor de cursos) ou uma
combinacao dos dois.
• Research Assistantship ligado a um projeto
especifico (suporte pedido no projeto) e dado
para o projeto (ao inves de para o aluno)
Como chegar la? graduacao
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Estamos costurando!
Ciencia sem fronteiras (?)
Estagio e cursos
Faremos contato direto entre professores
• Participacao com Penn State e Westinghouse
Conclusion
• Review of Penn State, world class research university and very
highly rated in nuclear engineering
• Review of research areas at Penn State
• Discussed how one can apply for graduate study
• Encourage you all to think about it, could have a major
difference in your career
END