Post on 12-Oct-2020
1
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
atm2@psu.edu
atm2@psu.edu
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
6
7
Views of Campus and Town
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• 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
13
THE ADVANCED MULTITHE ADVANCED MULTI--PHASE FLOW PHASE FLOW
LABORATORY (AMFL)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: jtalley@psu.edu
TWOTWO--PHASE FLOW TRANSPORT IN COMBINATORIAL CHANNELSPHASE FLOW TRANSPORT IN COMBINATORIAL CHANNELS
Sponsored by U.S. DOE Sponsored by U.S. DOE -- NEER Program; Continued by U.S. NRCNEER Program; Continued by U.S. NRC
L/D=7.5
L/D=34.5
L/D=61.5
L/D=3
L/D=93
L/D=177
L/D=1.5
L/D=15
L/D=66
L/D=3
L/D=87
L/D=165
1.5
25.5
49.5
• 5.08 cm ID acrylic test section
• Glass elbows
• Development length
Vertical: ~ 60D or ~3 m
Horizontal: ~180 or ~9 m
• Two inlet conditions
To study two-phase flow transport under the effects of geometric restrictions and orientations
P3; (L/D)V = 60
P4; (L/D)H = 3 P10; (L/D)H = 177
P11; (L/D)V = 1.5 P12; (L/D)V = 16.5
P7; (L/D)H = 93P5; (L/D)H = 30
Measured Void Fraction Profiles
jf=3.0 m/s & jg=0.35 m/s
P3; (L/D)V = 62 P11; (L/D)V = 1.5
P12; (L/D)V = 15
TRACE CODE DEVLEOPMNET USING TRACE CODE DEVLEOPMNET USING INTERFACIAL AREA TRANSPORT EQUATION INTERFACIAL AREA TRANSPORT EQUATION
Sponsored by U.S. NRCSponsored 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
• Eliminates bifurcation / numerical oscillation
• Significant improvements in code prediction results
Error bars shown: ±20%
Vertical Downward Air-WaterPipe Size: 2.54 cm ID
jg,loc,1= 0.453 m/s, jf= 3.110 m/s
The Advanced Multi-phase Flow Laboratory, Department of Mechanical and Nuclear EngineeringTel: (814) 867-0282 Email: jtalley@psu.edu
• 38.1 mm ID acrylic test section
• Adiabatic air-water
• L/D ~ 250 or 9.5 m
• Capable of comprehensive two-phase flow regimes
HORIZONTAL TWOHORIZONTAL TWO--PHASE FLOWPHASE FLOW
Sponsored by Bettis Atomic LaboratorySponsored by Bettis Atomic Laboratory
To establish database for CMFD code development at Bettis Atomic Power Laboratory
Igor JovanovicAssociate Professor of Nuclear Engineering
See http://www.mne.psu.edu/IJ for more info
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
Department of Mechanical and Nuclear Engineering & Radiation Science and Engineering Center
Radiation Science and Engineering CenterRadiation 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 Measurements of signature trace elements in dated tree ring samples to make correlations dated tree ring samples to make correlations
with environmental effects 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 Analysis of spent fuel samples with Compton Suppression System at RSECSuppression 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 Development of innovative radioactive isotope production techniques at RSECproduction 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 LaboratoryNew Radiochemistry Teaching Laboratory
Current Research Current Research
Bill Cheung Bill Cheung –– Professor of Mechanical & Nuclear EngineeringProfessor of Mechanical & Nuclear Engineering
Project #1: Project #1: Study the effects of spacer grids on heat transfer.Study the effects of spacer grids on heat transfer.
Sponsors:Sponsors: US Nuclear Regulatory Commission, Purdue Univ. Thermal US Nuclear Regulatory Commission, Purdue Univ. Thermal
Hydraulics InstituteHydraulics Institute
Project #2: Project #2: Conceptual design of core catcher in case of core accident Conceptual design of core catcher in case of core accident
for severe accident mitigation for Eufor severe accident mitigation for Eu--APR1400 APR1400
Sponsors:Sponsors: Korean Atomic Energy Research InstituteKorean Atomic Energy Research Institute
SPACERSPACER--GRID THERMALGRID THERMAL--HYDRAULICS (SGTH)HYDRAULICS (SGTH)Sponsored by U.S. NRCSponsored by U.S. NRC
• Reference System: 17x17 Westinghouse PWR
• 7x7 full length heated rod bundle assembly
Pressure oscillation damping tank
test section: 7x7 rod-bundle flow housing
upper plenum
lower plenum
steam separator
heated water supply tank
exhaust muffler
To study spacer-grid effects on the cooling of PWR fuel assemblies, including
the oscillating reflood conditions
Clad Temperatures at Constant Reflood Rates
2.54 cm/s (Run #5092) vs. 5.08 cm/s (Run #5086)
200
600
1000
1400
1800
0 100 200 300 400 500
Time (sec)
Te
mp
era
ture
(˚F
)
Exp 5092 D3 2.69 m (106")
Exp 5092 D3 2.80 m (110")
Exp 5086 D3 2.69 m (106")
Exp 5086 D3 2.80 m (110")
Reactor Dynamics and Fuel Management Group
Reactor Dynamics and Fuel Management Group (RDFMG) – research
group consisting of 18 graduate students and four faculty:
– 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/rdfmgwww.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
� Azimuthal profile because of differences in flux and in cooling around the clad circumference
November 2011 29
200µm
Miyashita 2007, Tsai & Billone 2002, Pyecha 1985
The project is based on the coupling of four simulation codes and a hydride model
FRAPTRAN
DeCART(Neutronic)
Cobra-TF(Thermohydraulic)
Hydride model
Cross-section library Off-line coupling CFD
Local Power
Hydride distribution(r,θ,z)
Boundary conditions
Local Power
Local bulk T
σ (r,θ,z)T (r,θ,z)[H] (r, θ,z)
Cross sections
30
At a given burn up
Burn-up
FRAPCON
[H]
31
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.
Consider as PWR representative a typical Westinghouse 4-loop pressurized water reactor core design with a 18-month high-burnup cycle
Reactor Core Designs
PB-2 BWR Loading Pattern
Typical PWR 18-Month Loading Pattern
30
2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 1 2 2 1 1 2 2 2 1 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 1 2 2 1 1 2 2 1 1 2 2 1 1 2 2 1 1 2 2
2 1 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 1 2
2 2 2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 1 2 2
2 2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 1 2 2 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 1 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 1 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 1 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 1 2
2 2 1 2 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 1 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 1 2 2 2 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 3 2 1 1 2
2 2 2 2 2 3 3 1 1 3 3 1 1 3 3 1 1 3 3 1 1 2 2 1 2 2
2 2 2 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 2 2 2
2 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 1
2 2 2 2 1 1 2 2 1 1 2 2 1 1 2 2 1 1 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3
2 2 2 2 2 2 2 2 2 2 2 2 2 2
30
Assembly Type 1
Assembly Type 2
Assembly Type 3
31
25 27 29 3117 19 21 239 11 13 151 3 5 7
2 4 6 8 10 12 14 16 18 22 24 26 2820
5
4
3
2
1
24
22
20
18
23
21
19
15
13
11
9
7
17
29
27
25
8
6
16
14
12
10
30
28
26
25 27 29 3117 19 21 23
26 28
1 3 5 7 9 11 13 15
18 20 22 2410 12 14 162 4 6 8
32
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
Multi-Physics Analysis
DeCart/TORT-TD
CTF
FRAPTRAN FRAPCON
Local power / linear heat rate
Local bulk temperature & density
Local fuel temperature
Initial fuel state
Local
power
Initial flow area
reduction
Local flow area reductionHeat transfer to coolant
Local pressureLocal bulk temperatureLocal surface HTC
Multi-physics high-fidelity simulation framework
33
Calculation Sequence
Pteparation of Multi-group Pin-
Cell Cross-Section Library
DeCart/TORT calculation of
Φn
Selection of Core locations for two
prototypical reactors using CASMO-4/SIMULATE-3
CTF calculation of mass flow rate, T
in coolant
Calculation of T(r,θ,z) by FRAPTRAN
Flowchart of Calculation Tasks
CTF sub-pin analysis capability for flexible azimuthal modeling of flux and temperature
distributions
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
MCNP/NEM/CTF –Accelerated Monte Carlo Calculations with Thermal-Hydraulic Feedback
Multi-Scale Multi-Physics System NEM/CTF/FRAPCON
TORT-TD/CTF coupling for High-Fidelity Calculations
RELAP-3D/COBRA-TFCoupling for LOCA Analysis
Faculty Participants: Prof. AvramovaLab/Center Name: RDFMGSponsor: AREVA NP, MHI, NECSA and GRS
Coupled 3-D Neutronics/Thermal-Hydraulic System Safety Analysis
Fully implicit coupling of TRACE and PARCS
Cross-section modeling for transient applications
Real –time simulators for operator training
Faculty Participants: Dr. Watson, Prof. Ivanov and Prof. AvramovaLab/Center Name: RDFMGSponsor: US NRC, GSE, Risk Engineering Ltd., ARL
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
mfratoni@psu.edu
MicroencapsulatedMetallic 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
M3 fuel consists of TRISO particles dispersed in a zirconium matrix
UO2
Pellet
ZircaloyCladding
Gap
Coated Fuel
Particle
Zr-Alloy Matrix
Conventional LWR UO2 Fuel Rod
Integral LWR M3 Fuel Rod
MicroencapsulatedMetallic 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 repositorythermal 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 repositorythermal 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 (once-through, modified open, and closed) were analyzed
Result example: large waste packagesare preferred for transportation but
they could require long surface storage
Razoes para se fazer pos graduacao
• Aprofundar conhecimentos• Fazer pesquisa• Aumentar sua marketabilidade• Mais $$$
Source:www.asme.org2011 salary survey
~$10,000/yr
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?
• 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
• 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