PHYSOR 2016

Transcription

PHYSOR 2016

PHYSOR 2016
Unifying Theory and Experiments in the 21st Century
Meeting Program
Honorary Chairs
James Lake,
Longnecker & Assocs.
Harold McFarlane,
Idaho National Laboratory (ret.)
General Chair
Finis Southworth, AREVA (ret.)
Assistant General Chairs
Danielle Perez, INL/IANS
Teri Ehresman, IANS
Financial Chair
Robert Skinner, IANS
Technical Program Chair
Mark DeHart, INL/IANS
The Physics of Reactors (PHYSOR) conferences represent a series of
international forums organized and sponsored to assemble expertise related to
reactor physics and related topical areas. PHYSOR 2016: Unifying Theory and
Experiments in the 21st Century, will be a venue focused on both
modeling/simulation & experimental aspects of reactor physics and exploration of
common aspects & requirements of the two focus areas. The meeting will also
include on an opening plenary, technical tours, workshops, and sessions in other
topics relevant to the physics of nuclear reactor systems. Special events are also
planned throughout the week, including a spouse/guest program.
PHYSOR will begin with a series of technical workshops Sunday morning,
followed by the Opening Reception Sunday evening. An Opening Plenary will be
held Monday morning, with a number of speakers widely known in the reactor
physics community. Technical sessions will begin Monday afternoon, running
through noon on Thursday. Seven parallel sessions are planned for each session
segment, with mid-morning and mid-afternoon breaks between sessions. Lunch
will be provided Monday – Wednesday.
If you have not yet registered for the meeting or conference hotel, both
registrations are available online at www.physor2016.org. This website also
contains a wealth of other information about the meeting and the area, including
options for getting to Sun Valley.
Assistant Technical Program
Chairs
Sun Valley is a resort city tucked
within the mountains of south
central Idaho, near the city of
Ketchum. It sits at the edge of the
Sawtooth and Challis National
Forests, with the Big Wood River, a
fisherman’s dream, running through
the Wood River Valley. Tourists
from around the world enjoy its
skiing, hiking, ice skating, trail
riding, tennis, and cycling. The
elevation of Sun Valley Lodge is
5920 feet (1804 m) above sea level.
Todd Palmer, Oregon State Univ.
Kent Welter, NuScale Power
Publications Chair
Germina Ilas, ORNL
Spouse Activity Chairs
Cindie Jensen, INL/IANS
Marinelle Rowe, INL/IANS
Student Arrangement Chair
Massimiliano Fratoni,
UC Berkeley
International Relations
Jim Gulliford, OECD/NEA
Deokjung Lee, UNIST
Jean-Pascal Hudelot, CEA
Sun Valley is a prominent year-round resort, with economic and environmental
sustainability, successful regional partnerships, social and cultural richness, and a
unique character and quality of life. Sun Valley enjoys a pleasant mountain desert
climate with an average humidity of only 30%. Its pristine mountains and pastures,
clean air and clean water make Sun Valley a highly desirable place to work, play,
live and visit.
hope to see you there!
We
Contents
PHYSOR 2016 Sponsors
4
Organizing Committee
5
Meeting Organizers
5
Technical Program Committee
6
Speaker and Poster Instructions
8
Sessions By Day
9
Technical Program
13
Monday Morning
13
Monday Afternoon
13
Monday Evening Poster Session
19
Tuesday Morning
22
Tuesday Afternoon
29
Wednesday Morning
34
Wednesday Afternoon
40
Thursday Morning
46
Exhibition Hall Map
50
Inn and Village Convention Facilities Map
51
Sun Valley Map
52
3
PHYSOR 2016 Sponsors
(As of Mar 28, 2016)
4
Organizing Committee
Honorary Chair
Honorary Chair
James Lake
Harold McFarlane
ANS Past President
ANS Past President
General Chair
Assistant General Chair
Assistant General Chair
Finis Southworth
Danielle Perez
Teri Ehresman
AREVA (ret.)
INL / Idaho American Nuclear Society
Idaho American Nuclear Society
Financial Chair
Robert Skinner
Idaho American Nuclear Society
Assistant Technical Program Chair
Assistant Technical Program Chair
Mark DeHart
Todd Palmer
Kent Welter
Oregon State University
NuScale Power
Publications Chair
Germina Ilas
Oak Ridge National Laboratory
Spouse Activity Chair
Spouse Activity Chair
Cindie Jensen
Marinelle Rowe
Student Arrangement Chair
Massimiliano Fratoni
University of California, Berkeley
Jim Gulliford
Deokjung Lee
Jean-Pascal Hudelot
OECD Nuclear Energy Agency
Ulsan National Institute of Science and Technology
Commissariat à l’Énergie Atomique et aux Énergies Alternatives
Meeting Organizers
ANS Idaho Section
Idaho National Lab
University of Idaho
Idaho State University
University of California at Berkeley
University of New Mexico
5
Technical Program Committee
Mark DeHart, Idaho National Laboratory/Chair, Idaho American Nuclear Society
Assistant Technical Program Chairs
Todd Palmer, Oregon State University
Kent Welter, NuScale Power
Committee Members
Hany Abdel-Khalik, Purdue University
Arzu Alpan, Westinghouse Electric Company
Yousry Y Azmy, North Carolina State University
John Bess, Idaho National Laboratory
Keith Bradley, Argonne National Laboratory
Blair Bromley, Canadian Nuclear Laboratories
Jon Carmack, Idaho National Laboratory
Go Chiba, Hokkaido University, Japan
Cassiano de Oliveira, University of New Mexico
Benoit Dionne, Argonne National Laboratory
Tom Downar, University of Michigan
Ronald Ellis, Oak Ridge National Laboratory
Romain Eschbach, Commissariat à l’Énergie Atomique et aux Énergies, France
Rodolfo Ferrer, Studsvik Scandpower, Inc.
Ben Forget, Massachusetts Institute of Technology
Massimiliano Fratoni, University of California at Berkeley
Katherin Goluoglu, Syzygy Solutions
Sedat Goluoglu, University of Florida
Qingzhen Guo, Halliburton
Ayman Hawari, North Carolina State University
Wei Ji, Rensselaer Polytechnic Institute
Zain Karriem, Idaho National Laboratory
Atul Karve, Global Nuclear Fuels - Americas
Dale Lancaster, NuclearConsultants.com
Luiz Leal, Oak Ridge National Laboratory
Chang Ho Lee, Argonne National Laboratory
Deok Jung Lee, Ulsan National Institute of Science and Technology, Korea
Jaakko Leppänen, VTT, Finland
Bill Martin, University of Michigan
Katheryn McCarthy, Idaho National Laboratory
Sean R Morrell, Idaho National Laboratory
David Nigg, Idaho National Laboratory
Javier Ortensi, Idaho National Laboratory
Scott Palmtag, Core Physics, Inc
Geoff Parks, Cambridge University, UK
Cheolho Pyeon, Kyoto University, Japan
Cristian Rabiti, Idaho National Laboratory
Sebastian Schunert, Idaho National Laboratory
Sonat Sen, Idaho National Laboratory
Wei Shen, Canadian Nuclear Safety Commission
Thomas Sutton, Knolls Atomic Power Laboratory
Temitope Taiwo, Argonne National Laboratory
Akira Tokuhiro, Purdue University
6
Wilfred van Rooijen, University of Fukui, Japan
Zeyun Wu, National Institute of Standards and Technology
Akio Yamamoto, Nagoya University, Japan
Won Sik Yang, Purdue University
Gilles Youinou, Idaho National Laboratory
Qiong Zhang, Baker Hughes Inc.
7
Speaker and Poster Instructions
•
Registration: All speakers must register to present. If you have not already registered,
please make sure to do so for the day(s) you are speaking or the full conference prior to
arriving on-site. If you have questions about registration, please contact the ANS
Registrar at registrar@ans.org regarding PHYSOR 2016
•
Pick up your badge and meeting materials at the Registration Desk (located outside the
Limelight Ballroom in the Sun Valley Inn).
Oral Presentations
•
On the day of your session, you are invited to the Speaker’s Breakfast in Limelight B.
You will have an opportunity meet your Session Chairs, who will be able to answer
any questions and make you aware of any changes that may have come up. You
should provide the Chair with a brief biography that can be used to introduce you at
your presentation.
•
Plan to report to the room assigned for your session (as listed in the Official
Program) 15 minutes prior to the start of the session. If you have not already done
so, please provide the Chair with a brief biography.
•
A computer and projector with screen will be provided for each session. You should
load and test your presentation on the computer prior to the session. If you need to
use your own laptop please advise your Session Chairs prior to the beginning of the
session.
•
Please limit your presentation to 20 minutes, allowing a five-minute discussion period
following the formal presentation of your paper. Your Session Chairs will advise you
as you near the end of your allotted time.
•
Please do not ask the Session Chair to reschedule your paper within the session.
Many attendees schedule their attendance at various sessions in accordance with
the times listed in the Official Program.
Poster Presentations
•
The Poster Session will be held Monday evening from 6-8pm in the Exhibition Hall.
Posters should be mounted between 4 and 5:30pm.
•
Two posters will be mounted side by side on each side of a 4’ (1.2 m) by 8’ (2.4 m)
cork bulletin board; hence posters should be no more than 4’ (1.2 m) in width.
Posters may be up to 6’ (1.8 m) tall, but the mounting surface is only 4’ (1.2 m) in
height.
•
Tacks will be provided for mounting posters. If a foam-core backing is used on your
poster, you should provide your own mounting tacks – provided tacks may not be
long enough.
•
Posters will be judged and the best poster will be recognized at the closing session
on Thursday.
Sessions By Day
Monday 8:00-12:15 PM
Opening Plenary: A Perspective on Nuclear Energy in the 21st Century - Opera House
Session Organizers: Dr. Finis H. Southworth (NGNP Industry Alliance), Mark DeHart (Idaho National
Laboratory)
Monday 1:30-3:35 PM
Fuel Cycle Physics, Management & Optimization I - Boiler
Diffusion Methods for Reactor Analysis - Camas
Depletion Methods I - Ram
Sensitivity/Uncertainty Analysis I - Sawtooth
Multi-Physics Reactor Simulations I - Limelight C
Nuclear Data, Evaluations & Libraries I - Columbine
Experiments I - Lupine
Monday 4:00-5:40 PM
Verification and Validation of Reactor Analysis Methods I - Camas
Transient Reactor Testing I - Ram
Depletion Methods II - Boiler
Full Core Analysis Methods I - Sawtooth
Multi-Physics Reactor Simulations II - Limelight C
Nuclear Data, Evaluations & Libraries II - Columbine
Sensitivity/Uncertainty Analysis II - Lupine
9
Monday 6:00-8:00 PM
Poster Session
Tuesday 8:00-9:40 AM
Fuel Cycle Physics, Management & Optimization II - 8:00-9:40 - Boiler
Noise-Based Methods Reactor Analysis - Camas
Nodal Methods for Reactor Analysis I - Columbine
Experiments II - Sawtooth
Multi-Physics Reactor Simulations III - Limelight C
Apollo Validation - Ram
Sub-Critical Systems I - Lupine
Tuesday 10:10 AM - 12:15 PM
Reactor Analysis Methods I - Boiler
Cross Section Methods for Reactor Analysis - Sawtooth
Recent Developments in Monte Carlo Codes and Methods I - Columbine
Research and Test Reactors - Camas
Sensitivity/Uncertainty Analysis III - Lupine
Multi-Physics Reactor Simulations IV - Limelight C
Advanced Multidimensional Reactor Kinetics Methods I - Ram
Tuesday 1:30-3:35 PM
Reactor Analysis Methods II - Boiler
Fast Reactors I - Camas
Depletion Methods III - Ram
MCNP Validation and Applications - Sawtooth
Validation Facilities - Lupine
Multi-Physics Reactor Simulations V - Limelight C
Nuclear Data, Evaluations & Libraries III - Columbine
10
Fuel Cycle Physics, Management & Optimization III - Boiler
Reactor Analysis Methods III - Sawtooth
Transient Reactor Testing II - Ram
Sub-Critical Systems II - Camas
Sensitivity/Uncertainty Analysis IV - Lupine
Advanced Multidimensional Reactor Kinetics Methods II - Limelight C
Nuclear Data, Evaluations & Libraries IV - Columbine
Wednesday 8:00-9:40 AM
Fuel Cycle Physics, Management & Optimization IV - Boiler
Reactor Dosimetry - Camas
Full Core Analysis Methods II - Columbine
Experiments III - Sawtooth
Advanced and Small Modular Reactor Designs I - Limelight C
Validation of Kinetics Methods - Ram
Validation of Thermal/Hydraulic Methods - Lupine
Wednesday 10:10 AM-12:15 PM
Reactor Analysis Methods IV - Boiler
Burn-up Credit and Spent Fuel Measurements - Limelight C
Recent Developments in Monte Carlo Codes and Methods II - Columbine
Verification and Validation of Reactor Analysis Methods II - Sawtooth
Modeling and Simulation for Nonproliferation and Safeguards - Camas
SCALE Validation - Lupine
Advanced and Small Modular Reactor Designs II - Ram
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Wednesday 1:30-3:35 PM
Reactor Analysis Methods V - Limelight C
Fast Reactors II - Camas
Verification and Validation of Reactor Analysis Methods III - Columbine
Recent Developments in Monte Carlo Codes and Methods III - Sawtooth
Finite Element Methods for Reactor Analysis - Boiler
Sensitivity/Uncertainty Analysis V - Lupine
Advanced and Small Modular Reactor Designs III - Ram
Full Core Analysis Methods III - Boiler
Multi-Physics Reactor Simulations VI - Limelight C
Reactor Operation and Control - Sawtooth
Nodal Methods for Reactor Analysis II - Camas
Nuclear Data, Evaluations & Libraries V - Columbine
Sensitivity/Uncertainty Analysis VI - Lupine
Advanced and Small Modular Reactor Designs IV - Ram
Thursday 8:00-10:05 AM
Experiments IV - Sawtooth
Fast Reactors III - Camas
Multi-Physics Reactor Simulations VII - Limelight C
Reactor Analysis Methods VI - Boiler
Monte Carlo Methods - Columbine
Verification and Validation of Reactor Analysis Methods IV - Ram
Sensitivity/Uncertainty Analysis VII - Lupine
Thursday 10:30 AM-12:00 PM
Awards and Closing - Limelight A & B
12
MONDAY AFTERNOON
Technical Program
Monday 8:00-12:15 PM
Opening Plenary: A Perspective on Nuclear Energy in the 21st Century - Opera House
Session Organizers: Dr. Finis H. Southworth (NGNP Industry Alliance), Mark DeHart (Idaho National
Laboratory)
Speakers:
Finis Southworth, (NGNP Industry Alliance)
William Magwood IV, Director-General of the Nuclear Energy Agency of the OECD
Chris Levesque, President of TerraPower, LLC
Mark Peters, Laboratory Director, Idaho National Laboratory
Monday 1:30-3:35 PM
Fuel Cycle Physics, Management & Optimization I - Boiler
Organized by: Geoff PARKS Cambridge University and Temitope TAIWO Argonne National Laboratory
Chairs: Gilles YOUINOU, Idaho National Laboratory and Ashlea COLTON, Canadian Nuclear Laboratories
1:30
1:55
2:20
2:45
3:10
A Multi-Batch Approach for Enhanced Plutonium Incineration in the Thorium-Based I2SLWR Design
Impact of Modifications in Continuous Recycling System for U/Pu and U/TRU with Fast
and Thermal Reactors on Fuel-Cycle Performance and Waste Characterization
Sensitivity Analysis of the Recycling Process
at the Second Stage of the PWR-ADS Fuel Cycle
Optimization of Axially Independent Zons of
PWR Assemblies in Full Core with Genetic Algorithms for Fresh Cycles
Economy of BR2 Fuel Cycle with Gadolinium
as Burnable Absorber
Dan Kotlyar, Geoffrey T. Parks
Hikaru Hiruta, Gilles J. Youinou, Brent W.
Dixon
Shengcheng Zhou, Youqi Zheng, Hongchun
Wu, Liangzhi Cao
Gregory M. Borza, Kostadin N. Ivanov, Tom
Carter
Silva Kalcheva, Edgar Koonen
Diffusion Methods for Reactor Analysis - Camas
Organized by: Thomas SUTTON, Knolls Atomic Power Laboratory and Deokjung LEE, Ulsan National
Institute of Science and Technology
13
MONDAY AFTERNOON
Chairs: Sebastian SCHUNERT Idaho National Laboratory and Zheng YOUQI, Ulsan National Institute
of Science and Technology
1:30
1:55
2:20
2:45
3:10
The Empirical Interpolation Method Applied to
the Neutron Diffusion Equations with Parameter Dependence
Unstructured Mesh, Abandonment from Diffusion Approximation in the Method of Surface
Harmonics
Multi-Group 1D-Reflector Modelling for EDF
PWR
Investigation of Diffusion Coefficient Calculation Methods for Two-Step LWR analysis
Eigenvalue Problem of the Neutron Diffusion
Equation with ADF and Discretized with the
FVM - Application to a PWR Modelled with Unstructured Grid
Helin Gong, Jean-Philippe Argaud, Bertrand
Bouriquet, Yvon Maday
Aleksandr Vsevolodovich Elshin
Seav Er Huy
Sooyoung Choi, Deokjung Lee, Kord S. Smith
Alvaro Bernal, Rafael Miro, Gumersindo
Verdu, Jose Enrique Roman, J. A. Bermejo
Depletion Methods I - Ram
Organized by: Rodolfo FERRER Studsvik Scandpower and Akio YAMAMOTO, Nagoya University
Chairs: Rodolfo FERRER Studsvik Scandpower and Akio YAMAMOTO, Nagoya University
1:30
1:55
2:20
2:45
3:10
Generalized Depletion Chain Simplification
Based on Significance Analysis
New Features and Capabilities in the VESTA
2.2 Monte Carlo Depletion Software
FISPACT-II: an Advanced Simulation Platform
for Inventory and Nuclear Observables
Validation of HORUS-3D/N Against TRIPOLI4D for Core Depletion Calculations of the Jules
Horowitz Reactor
Implementation of Inline Equilibrium Xenon
Method in RMC Code
14
Kai Huang, Hongchun Wu, Yunzhao Li,
Liangzhi Cao
Wim Haeck, Cochet Bertrand, Alexis Jinaphanh
Jean-Christophe C. Sublet, M. Fleming, M. R.
Gilbert, J.W. Eastwood, J.G. Morgan
Amalia Chambon, Paolo Vinai, Christophe Demazière, Lionel Gaubert, Florence Jeury, J.
Politello, Patricia Siréta
Feng Yang, Gang Wang, Zonghuan Chen,
Ganglin Yu, Kan Wang
MONDAY AFTERNOON
Sensitivity/Uncertainty Analysis I - Sawtooth
Organized by: Cristian RABITI Idaho National Laboratory and Hany ABDEL-KHALIK, Purdue University
Chairs: Hany ABDEL-KHALIK, Purdue University and Maria PUSA, VTT Technical Research Centre of
Finland
1:30
Verification, Validation and Uncertainty Quantification for Neutronic Calculation for ASTRID
Fast Reactor Detailed Design
1:55
BERING: Data Assimilation and Uncertainty
Quantification for Safety Assessment Support
Use of Advanced UQ Approaches to the Validation of the IRDFF Library
Sensitivities and Uncertainties Due to Nuclear
Data in a Traveling Wave Reactor
Uncertainty Quantification of Delayed Neutron
Fraction of U235 Bases Fuel Cores
2:20
2:45
3:10
Cyrille De Saint Jean, Benedicte Roque, Gerald Rimpault, Pascal Archier, Jean-Francois
Vidal, Jean-Marc Palau, Jean Tommasi, Bruno
Fontaine, Frederic Varaine
Evgeny A. Ivanov
Patrick J. Griffin, Edward J. Parma, David Vehar
Nicholas W. Touran, Jinan Yang
Gerald Rimpault, David Blanchet, Paul Dufay,
Jean Tommasi, Guillaume Truchet
Multi-Physics Reactor Simulations I - Limelight C
Organized by: Wei JI, Rensselaer Polytechnic Institute, Cassiano DE OLIVEIRA, Unviersity of New
Mexico and Mark DeHART Idaho National Laboratory
Chairs: Hongbin ZHANG, Idaho National Laboratory and Tuomas VIITANEN, VTT Technical Research
Centre of Finland
1:30
1:55
2:20
2:45
3:10
Application of a Probabilistic Relationship Diagram for PDE Mechanical Energy Release
Evaluation after HCDA in a Sodium-Cooled
SMR
Neutronics Benchmark for EBR-II Shutdown
Heat Removal Test SHRT-45R
Impact of Radial Void Fraction Distribution on
Boiling Water Reactor Lattice Physics Calculations: Application to AREVA’s Next Generation BWR fuel Assembly, the ATRIUM™ 11™
Design.
Coupled MC21 and COBRA-IE Solution to
VERA Core Physics Benchmark Problem #6
Coupling Serpent and OpenFOAM® for Neutronics - CFD Multi-Physics Calculations
Fabrizio Gabrielli, Michael Flad, Simone Gianfelici, Rui Li, Vladimir Kriventsev, Werner
Maschek, Claudia Matzerath Boccaccini, Barbara Vezzoni, Andrei Rineiski
Tingzhou Fei, Barbara Vezzoni, Marco
Marchetti, Willem F. van Rooijen, Youpeng
Zhang
Alexander S. Bennett, Nicolas P. Martin, Maria
N. Avramova, Kostadin N. Ivanov
Brian N. Aviles, Daniel J. Kelly, David L. Aumiller, Daniel F. Gill, Brett W. Siebert, Andrew
T. Godfrey, Benjamin S. Collins, Robert K.
Salko
Riku Tuominen, Ville Henrikki Valtavirta, Juho
Peltola, Jaakko I. Leppänen
Nuclear Data, Evaluations & Libraries I - Columbine
Organized by: Luiz LEAL, Institut de Radioprotection et de Sûreté Nucléaire, Ayman HAWARI, North
Carolina State University and Go CHIBA, Hokkaido University
Chairs: Michael DUNN, Oak Ridge National Laboratory and Luiz LEAL, Institut de Radioprotection et de
Sûreté Nucléaire
15
MONDAY AFTERNOON
1:30
1:55
2:20
2:45
3:10
Generation of Thermal Neutron Scattering
Cross Sections of MgF2 Using Ab Initio Lattice
Dynamics Calculations
A Study of the Effects of Self-Shielding and
Cross Section Library on Fast Reactor Critical
Benchmarks
Computational Methods Used to Process
Thermal Neutron Scattering Data for Use in
Continuous Energy Monte Carlo Codes
Optimal Knot Reduction in Cubic Spline Interpolation of ORIGEN’s Reactor Libraries
Use of integral experiments to test a new 235U
evaluation for the CIELO project.
Iyad I. Al-Qasir, Abdallah Qteish
Huseyin Atila Ozgener, Bilge Ozgener
Timothy H. Trumbull
Guojun Hu, William Wieselquist
Raphaelle Ichou, Nicolas Leclaire, Luiz Leal,
Evgeny A. Ivanov, W. Haeck
Experiments I - Lupine
Organized by: John BESS Idaho National Laboratory, Arzu ALPAN, Westinghouse Electric Company
and Cheolho PYEON, Kyoto University
Chairs: Margaret MARSHALL, Idaho National Laboratory and Laurent CHABERT, AREVA-France
1:30
1:55
2:20
COG Validation for Foil and TLD Irradiation in
a SILENE Criticality Excursion Benchmark Experiment
Fast-Thermal Coupled Cores in ZPR revisited
- Physical specificities and potentialities for
ZEPHYR
Benchmark Experiments at the TRIGA MARK
II Reactor
2:45
Spectrum Index and Minor Actinide Fission
Fate Measurements in Several Fast LeadBased VENUS-F Zero Power Critical Cores
3:10
Neutron Flux Distribution Measurements for
BWR Control Rods in Critical Experiments
16
Soon Sam Kim, Dave Heinrichs, Rich Buck,
Ed Lent, Chuck Lee
Paul Ros, Pierre Leconte, Patrick Blaise,
Jacques Di-Salvo
Luka Snoj, Ziga Stancar, Vladimir Radulovic,
Tanja Kaiba, Gasper Zerovnik, Igor Lengar,
Vid Merljak, Andrej Trkov, Loic Barbot, Damien
Fourmentel, Vladimir Radulovic, Christophe
Destouches, Jean-Francois Villard
Anatoly Kochetkov, A. Krasa, G. Vittiglio, J.
Wagemans, A.G. Bianchini, V. Fabrizio, M.
Carta, G. Firpo, E. Fridman, M. Sarotto, V. Becares
Tsukasa Sugita, Hiroshi Matsumiya, Tsukasa
Kikuchi, Kenichi Yoshioka, Satoko Tajima,
Masaru Ukai, Yamato Hayashi, Tadaaki Shimazu
MONDAY AFTERNOON
Monday 4:00-5:40 PM
Verification and Validation of Reactor Analysis Methods I - Camas
Chairs: Thomas DOWNAR, University of Michigan and Kazufumi TSUJIMOTO, Japan Atomic Energy
Agency
4:00
Solution of the OECD/NEA SFR Neutronic
Benchmark Using WIMS and MONK
4:25
Verification of the 3D Method of Characteristics Solver in OpenMOC
Validation of ADVANTG Best-Estimate Dose
Evaluations for the NAC MAGNASTOR® Dry
Storage Case Systems at Zion
Validation of the SPn Depletion Schemes Of
The EDF GABV2-COCAGNE Tools Using the
KAIST 1A Benchmark.
4:50
5:15
Ben Stray, Matthew Delaney, Ben Lindley,
Max Shepherd, Simon Richards, Glynn Hosking, Peter Smith
Samuel C. Shaner, Geoffrey A. Gunow, Kord
S. Smith, Benoit Forget
Victor G. Smith, Ethan Taber, Brandon Distler
Ansar Calloo, Seav Er Huy, David Couyras,
Coline Brosselard, Marie Fliscounakis
Transient Reactor Testing I - Ram
Organized by: Javier ORTENSI and Dan WACHS, Idaho National Laboratory
Chairs: Javier ORTENSI, Idaho National Laboratory and Jean-Pascal HUDELOT, Commissariat à
l’Énergie Atomique et aux Énergies Alternatives
4:00
4:25
4:50
Preliminary Modeling to Support the TREAT
Hodoscope System for Fuel Motion Monitoring
Thermal-Hydraulic Response of the TREAT
Multi-Vessel Static Environment Test Vehicle
MCNP Water Physics Scoping Study to Support LWR Accident Tolerant Fuel Testing in
TREAT
Scott J. Thompson, Clive H. Townsend, David
Chichester
Colby B. Jensen, Charles P. Folsom, Cliff
B. Davis, Nicolas Eric Woolstenhulme, Heng
Ban, Robert C. O’Brien, Daniel M. Wachs
Connie M. Hill, John Bess, Sam Bays, Nicolas
Eric Woolstenhulme, James R. Parry
Depletion Methods II - Boiler
Chairs: Joshua HYKES, Studsvik Scandpower and Go CHIBA, Hokkaido University
4:00
4:25
4:50
Log-Linear Substep Method for Monte Carlo
Depletion Coupled Codes
Use of 2sPC Depletion Scheme in UWB1 Nuclear Fuel Depletion Code for the Assessment
of Burnable Absorber Fuel Design
Techniques for Practical Monte Carlo Reactor
Depletion Calculations
17
Dan Kotlyar, Eugene Shwageraus
Martin Lovecky, Radek Skoda
David P. Griesheimer, David C. Carpenter,
Mark H. Stedry
MONDAY AFTERNOON
5:15
Nuclide Depletion Capabilities in the Shift
Monte Carlo Code
Gregory G. Davidson, Tara M. Pandya, Aarno
Isotalo, Seth R. Johnson, Thomas M. Evans,
William Wieselquist
Full Core Analysis Methods I - Sawtooth
Chairs: Scott PALMTAG, Core Physics, Inc. and Yohei KAMIYAMA, Mitsubishi Heavy Industries
4:00
4:25
4:50
5:15
Neutronic Modeling of the MYRRHA Minimum
Critical Core with PARCS and Serpent
Reactivity Assessment of Enhanced Accident
Tolerant Claddings in a Modern PWR
Development of a Production MCNP CANDU
3D Full-Core Model with Practical Remedies to
the Issues in Deriving Reliable Tally Results
Monte Carlo Simulation on Krsko NPP
Jeremy Bousquet, Armin Seubert, Kiril Velkov,
Frank-Peter Weiss
Troy Eckleberry, G. Ivan Maldonado
Wei Shen, Jingliang Hu
Dusan Calic, Andrej Trkov
Multi-Physics Reactor Simulations II - Limelight C
Chairs: Richard MARTINEAU Idaho National Laboratory and Christophe DEMAZIÈRE, Chalmers University
4:00
4:25
4:50
5:15
Sensitivity of Fuel Rod CRUD Deposition Modeling: CRUD Properties and Boundary Condition Effects
Sensitivity of Fuel Rod CRUD Deposition Modeling: Feedback Effects of Neutronics and
Thermal Hydraulics
Neutronic Calculation of Deformed Cores:
Development of a Time-Dependent Diffusion
Solver in CAST3M, a Mechanics Dedicated Finite Element Code
Interests of the Improved Quasi-Static Method
for Multi-Physics Calculations Illustrated on a
Neutronics-Thermomechanics Coupling
18
Daniel J. Walter, Brian K. Kendrick, Victor
Petrov, Annalisa Manera
Daniel J. Walter, Victor Petrov, Brian K.
Kendrick, Annalisa Manera
Cyril Patricot, Olivier Fandeur, Anne-Marie
Baudron, Daniel Broc, Jean-Charles Le Pallec
Cyril Patricot, Olivier Fandeur, Anne-Marie
Baudron, Jean-Charles Le Pallec
MONDAY EVENING POSTER SESSION
Nuclear Data, Evaluations & Libraries II - Columbine
Chairs: Sedat GOLUOGLU University of Florida and Luiz LEAL, Institut de Radioprotection et de Sûreté
Nucléaire
4:00
4:25
4:50
5:15
Benchmark Tests of Newly-Evaluated Data of
U-235 for CIELO Project Using Integral Experiments of Uranium-Fueled FCA Assemblies
On-The-Fly Doppler Broadening of Unresolved Resonance Region Cross Sections Via
Probability Band Interpolation
Re-Evaluation of the Eu-154 Thermal Capture
Cross-Section Based on Spent Fuel Benchmarking Studies
Activation Experiments for Verification of Neutron Capture Cross Section of 237Np Using
Variable Neutron Field at KURRI-LINAC
Masahiro Fukushima, Yasunori Kitamura,
Kenji Yokoyama, Osamu Iwamoto, Yasunobu
Nagaya, Luiz Leal
Jonathan A. Walsh, Benoit Forget, Kord S.
Smith, Forrest B. Brown
Steve E. Skutnik, Nathan T. Shoman
Yoshiyuki Takahashi, Jun-ichi Hori, Tadafumi
Sano, Takahiro Yagi, Hiroshi Yashima, Cheolho Pyeon, Shoji Nakamura, Hideo Harada
Sensitivity/Uncertainty Analysis II - Lupine
Organized by: Cristian RABITI Idaho National Laboratory and Hany ABDEL-KHALIK
Chairs: Brett RAMPAL NuScale Power and Kensuke KOJIMA Japan Atomic Energy Agency
4:00
4:25
4:50
5:15
Efficient Active Subspace Identification via
MLROM
Reducibility of the INL’S MAMMOTH Coupled
Code System for Reactor Analysis
Burn-up Sensitivity Analysis of Minor Actinide
Transmutation Fast Reactor
Sensitivities and Uncertainties of Reaction
Rate Ratios in PWR Cells with UO2 and MOX
Fuel
Mohammad G. Abdo, Hany S. Abdel-Khalik
Dongli Huang, Hany S. Abdel-Khalik, Frederick N. Gleicher, Congjian Wang, Cristian Rabiti
Tadafumi Sano, Toshikazu Takeda
Basma Foad, Toshikazu Takeda
Monday 6:00-7:30 PM
Poster Session
Heterogeneous Multigroup Cross Sections for Fast
Reactor Calculations with MCC-3/PROTEUS
Michael G. Jarrett, Emily Rena Shemon, Changho
Lee
IAEA EBR-II Neutronics Benchmark: Impact of Modeling Options on KIT Results
Barbara Vezzoni, Marco
Gabrielli, Andrei Rineiski
Efficacy of Hardware Threading for Monte Carlo Particle Transport Calculations on Multi- And ManyCore Systems
Paul K. Romano
19
Marchetti,
Fabrizio
A Progressive Incremental Adjustment Methodology
for Cross-Section and Variance/Covariance Data
Adjustment for Fast-Spectrum Systems
Sandro Pelloni
Validation of a Multi-Purpose Depletion Chain for
Burnup Calculations Through TRIPOLI-4D Calculations and IFP Perturbation Method
Pascal Archier, Sylvia M. Domanico, Jean-Marc
Palau, Guillaume Truchet
NuScale Power Software Commercial Grade Dedication for Reactor Physics Calculations and Analyses
Renae N. Lenhof, Allyson K. Kitto, Brett D. Rampal,
Brian Matthews, Zain Karriem
Recent Development on New Monte Carlo Model for
Reactor Operating Control
Laurent Chabert, Simon Nicolas, Nicolas Gandoin
Use of Spectral Shift to Greatly Improve Uranium
Utilization in Single-Batch SMRs: Three Conceptual
Designs
Ben Lindley, Dan Kotlyar, Geoff Thomas Parks
Control Rod Measurements by Rod Insertion Using Signal from Multiple Fission Chambers at TRIGA
Reactor
Igor Lengar, Vid Merljak, Marjan Kromar, Luka Snoj
First Core Design tor the I2S-LWR 18-Month Cycle
Dan Kotlyar, Sai Li, Geoffrey T. Parks, David A.
Salazar, Fausto Franceschini, Bojan Petrovic
Total Sensitivity and Uncertainty Analysis Code Development for Neutron-Physics Calculations
Tiejun Zu, Chenghui Wan, Liangzhi Cao, Hongchun
Wu
Evaluation of the CASL BWR Fuel Assembly Benchmark using the TRANSLAT Lattice Physics Code
with 16-Sector Fuel Cells
Dean B. Jones
ZPPR Benchmark Exercise using APOLLO3
Igor Zmijarevic, Tamara Martinez, Li Mao
Impact of Fast Reactor Technology on U/Pu And
U/TRU Continuous Recycle Fuel Cycles
Nicolas E. Stauff, E. A. Hoffman, T. K. Kim, T. A.
Taiwo
Limited Collision Monte Carlo Method for Acceleration of Reactor Core Calculations
Kendra P. Keady, Edward W. Larsen
Dynamics of the TREAT Reactor Control System
Vishal Patel
Estimation of the Zero-Power Reactor Transfer from
a 3-Dimensional Core Simulator in the Frequency
Domain
Christophe Demaziere, Victor Dykin
Improvement of the Cross Sections Library Generation Within Full Core Configuration for 3D Neutron
Calculation of OSIRIS MTR Reactor in ANUBIS V3
aith Verification and Validation
Franck Lopez, Fadhel Malouch
Development of an Efficient Approach to Perform
Neutronics Simulations for Plutonium-238 Production
David Chandler, Ronald Ellis
20
In-Core Neutron Detectors for Characterizing High
Temporal-Resolution Reactor Transients
Jan Izak Cornelius Vermaak, Sophit Pongpun, Marvin L. Adams, Thomas J. Conroy
Advanced Applications of Natural Gamma Ray Well
Logging Tools
Qingzhen Guo, Weijun Guo
A Comprehensive Numerical Modelling of a Fission
Chamber to be Operated over a Wide Dynamics in
the Vessel of a Sodium-Cooled Reactor
Philippe Filliatre, Christian Jammes
Comparison of Deterministic and Monte Carlo
Codes SUSD3D, Serpent and XSUSA for BetaEffective Sensitivity Calculations
Ivan Alexander Kodeli, Manuele Aufiero, Winfried
Zwermann
Neutronic Analysis of Commercial PWR Cores Using Two Accident Tolerant Fuels
Daehee Hwang, Ser Gi Hong
Development of a Reactor Core Physics Analysis
Code in COSINE Project
Changhui Wang, Guoping Quan, Su Wang, Zhanquan Liu, Chen Yixue
Xenon Stability Analysis of the NuScale Small Modular Reactor
Zain Karriem, Allyson K. Kitto, Kenny Anderson
Xenon 135M in Nuclear Thermal Propulsion
Michael J. Eades, Paolo F. Venneri
Initial Verification of High-Fidelity Transport Code
PROTEUS using Thermal Reactor Benchmarks
Ana Jambrina Gomez, Changho Lee, Kostadin N.
Ivanov
Participation in OECD/NEA Benchmarks For LWRs
Modelling Using SCALE6.2 Code
Consuelo Gómez-Zarzuela, Antonella Labarile,
Rafael Miro Miró, Carles Mesado Mesado, Teresa
Barrachina, Gumersindo Verdú
Verification of Adjoint-Weighted Tally Calculation
Capability in MCS
Yunki Jo, Deokjung Lee
Research and Implementation of Hybrid Parallel Algorithm in Monte Carlo Criticality and Burnup Calculation
Feng Yang, Jin-gang Liang Ding She Ganglin YU,
Kan Wang
Influence of Nuclear Data on Fast Reactor Calculations
Friederike Bostelmann, Frank-Peter Weiss, Alexander Aures, Kiril Velkov, Winfried Zwermann, Bradley
T. Rearden, Matthew A. Jessee, Mark L. Williams,
Dorothea Wiarda, William Wieselquist
Performance Study of a Parallel Domain Decomposition Method
Nans Odry, Jean-Francois Vidal, Gerald Rimpault,
Jean-Jacques Lautard, Anne-Marie Baudron
Comparative Analysis of Fuel Performance Models
using Sub-Channel Code CTF, and High Fidelity
Fuel Performance Codes FRAPCON and BISON
Faisal Zahur Raja, Michael G. Mankosa, Maria N.
Avramova
FW/CADIS-Omega: an Angle-Informed Hybrid
Method for Deep-Penetration Radiation Transport
Madicken Munk, Rachel N. Slaybaugh, Tara M.
Pandya, Seth R. Johnson, T. M. Evans
An Analytical Approach to Deriving Diffusion Coefficient for P0 Transport-Correction
Ben C. Yee, Edward W. Larsen, Brendan Kochunas
21
TUESDAY MORNING
Xenon Induced Spatial Oscillations - a Pattern Formation Approach
Nir Kastin, Ehud Meron, Assaf Kolin, Shai Kinast
Integrated and High-fidelity Simulation Capability of
SuperMC for Fission Applications
Jing Song, Liqin Hu, Pengcheng Long, Tao He, Lijuan Hao, Mengyun Yun Cheng, Huaqing Zheng,
Shengpeng Yu, Guangyao Sun, Tongqiang Dang, Qi
Yang, Bin Wu, Chaobin Chen, Ling Fang, Yican Wu
Tuesday 8:00-9:40 AM
Fuel Cycle Physics, Management & Optimization II - 8:00-9:40 - Boiler
Chairs: Nicoloas STAUFF, Argonne National Laboratory and Marc ERNOULT, Japan Atomic Energy
Agency
8:00
8:25
8:50
9:15
Assessment and Benchmarking with ORION
and Cyclus for US Fuel Cycle Options
Generation of SFR Physics Models for the Nuclear Fuel Cycle Code CLASS
Use of Quasi-Monoenergetic Laser Compton
Scattering Beam for Enhanced Transmutation
of Nuclear Waste
PWR MOX Fuel Physics Models for the Dynamic Fuel Cycle Simulation Tool CLASS
Jennifer L. Littell, Andrew Worrall, Eva E.
Sunny, Steve Eugene Skutnik
Baptiste Leniau, Fanny Courtin, Baptiste
Mouginot, Nicolas Thiolliere, Xavier Doligez,
Adrien Bidaud
Haseeb ur Rehman, Jiyoung Lee, Yonghee
Kim
Fanny Courtin, Baptiste Leniau, Baptiste
Mouginot, Nicolas Thiolliere, Xavier Doligez,
Alice Somaini, Adrien Bidaud
Noise-Based Methods Reactor Analysis - Camas
Chairs: Andrew SIEGEL, Argonne National Laboratory and Imre PAZSIT, Chalmers University
8:00
8:25
8:50
9:15
A New Monte Carlo Method for Neutron Noise
Calculations
On Causality Analysis of Nuclear Reactor
Noise Using Partial Directed Coherence
Analysis of Critical and Subcritical Neutron
Noise Experiments in MINERVE Using Advanced Noise Techniques
The Effect of the Correlation Length on the
Propagation Neutron Noise Generated Inside
a Core in Light Water Reactors”
Nodal Methods for Reactor Analysis I - Columbine
22
Amelie Rouchon, Andrea Zoia, Richard
Sanchez
Dionysios A. Chionis, Abdelhamid Dokhane,
Hakim Ferroukhi, Andreas Pautz
Erez Gilad, Assaf Kolin, Oleg Rivin, Chen
Dubi, Benoit Geslot, Patrick Blaise
Victor Dykin, Imre Pazsit
TUESDAY MORNING
Organized by: Thomas DOWNAR, University of Michigan and Kent WELTER, NuScale Power
Chairs: Thomas DOWNAR, University of Michigan and Zheng YOUQI, Ulsan National Institute of Science
and Technology
8:00
8:25
8:50
9:15
Variational Nodal Method Fission-Source Iteration Acceleration using the Partitioned-Matrix
Technique
Microscopic Depletion with the Correction of
Microscopic Cross Sections in Nodal Diffusion
Code DYN3D
Multi-Group GMRES Algorithm for the Exponential Function Expansional Nodal SP3
Method
Nodal Diffusion Methods: Understanding Numerous Unpublished Details
Yunzhao Li, Boning Liang, Hongchun Wu,
Liangzhi Cao
Yurii Bilodid, Dan Kotlyar, Eugene Shwageraus, Emil Fridman, Soeren Kliem
Wen Yang, Hongchun Wu, Yunzhao Li,
Liangzhi Cao
Kord S. Smith
Experiments II - Sawtooth
Chairs: John BESS Idaho National Laboratory and Kazufumi TSUJIMOTO, Japan Atomic Energy
Agency
8:00
Nuclear Radiation Heating Measurements in
the University of Wisconsin Nuclear Reactor
8:25
Benchmark Development for TREAT Minimum
Critical Mass Core Loading to Support Validation of TREAT Operations
Benchmarking of the Graphite and Fluoride
Salt Insertions in LR-0 Reactor
8:50
9:15
A New Approach to Nondestructive Testing of
Fuel Column under Irradiation
23
Edward Kent, Mark H. Anderson, Timothy H.
Trumbull, Edwin Grant, Laura Bartol, Paul
Brooks, Kyle W. Schmalzer, Reem Almehisni,
Robert Agasie
John D. Bess, Benjamin Chase, James Parry
Evzen Losa, Michal Košál, Vojtìch Rypar, Martin Schulc, Evžen Novák, Bohumil Jánský,
Martin Veškrna, Filip Mravec, Zdenìk Matìj,
František Cvachovec
Ekaterina Ryabikovskaya, Vitaly I. Surin
TUESDAY MORNING
Multi-Physics Reactor Simulations III - Limelight C
Chairs: Chang Ho LEE, Argonne National Laboratory and James DYRDA, Oranization for Economic
Cooperation and Development
8:00
8:25
Three-Dimensional Modeling of Hydrogen
and Hydride Distribution in Zirconium Alloy Cladding Using High-Fidelity Multi-Physics
Simulations
AP1000® PWR Cycle 1 HFP Depletion Simulations with VERA-CS
8:50
Simulation of Crud Induced Power Shift using
the VERA Core Simulator and MAMBA
9:15
Coupled Neutronics and Thermal-Hydraulics
Calculation Code Development for Molten Salt
Reactor
Maria N. Avramova, Kostadin N. Ivanov, Annalisa Manera, Michael G. Mankosa, Victor Petrov, Daniel J. Walter, Richard L.
Williamson, Stephen R. Novascone
Fausto Franceschini, David A. Salazar, Andrew Godfrey, Shane Stimpson, Benjamin S.
Collins, Cole Gentry, Mohamed Ouisloumen
Benjamin S. Collins, Robert K. Salko, Scott
Palmtag, Kevin T. Clarno, Jeffery R. Secker,
Brian Kendrick, Shane Stimpson, Andrew
Godfrey, Rosemary Montgomery
Hongchun Wu, Kun Zhuang, Liangzhi Cao,
Yunzhao Li, Tianliang Hu
Apollo Validation - Ram
Chairs: Zain KARRIEM, Idaho National Laboratory and Evgeny IVANOV, Institut de Radioprotection et
de Sûreté Nucléaire
8:00
8:25
8:50
9:15
Improvement of the Verification and Validation
Methodology for the New CEA APOLLO3(R)
Neutronic Code
Development and Validation of a New
APOLLO-Based Calculation Scheme Dedicated to Isabelle1 Ex-Core Rod Irradiations in
the OSIRIS MTR Reactor
Validation of the New Code Package
APOLLO2.8 for Accurate BWR Calculations
Validation of the APOLLO2.8 Code Package
for the Calculation of Effective Kinetics Parameters and the Reactivity Versus Reactor Period
Relationship
24
Valentin Jouault, Jean-Marc Palau, Gerald
Rimpault, Pascal Archier, Vincent Pascal,
Benedicte Roque, Jean-Francois Vidal
Thibault Daullé, F. Chevallier, F. Malouch
Alain Santamarina
Pierre Leconte, Alain Santamarina, JeanFrancois Vidal, Patrick Blaise, Guillaume
Truchet
TUESDAY MORNING
Sub-critical systems I - Lupine
Organized by: Massimiliano FRATONI University of California, Berkeley, Won Sik YANG, Purdue University and Takanori KITADA, Osaka University
Chairs: Margaret MARSHALL, Idaho National Laboratory and Adimir DOS SANTOS, Instituto de
Pesquisas Energéticas e Nucleares
8:00
8:25
8:50
9:15
Experimental Benchmarks on Subcriticality in
Accelerator-Driven System with 100 MeV Protons at Kyoto University Critical Assembly
Deterministic Analyses of the Phase-I Kinetics
Experiments in the KUCA Subcritical A-Core
Configurations
Analysis on the Effect of High Energy Neutron
Source in ADS Neutronics Calculation
Analysis of Subcritical PWR and AGR Cores
using WIMS and PANTHER
Cheolho Pyeon, Masao Yamanaka, Yoshiyuki
Takahashi
Fabrizio Gabrielli, Andrei Rineiski, Alberto
Talamo, Mohamed Yousry Gohar, Cheolho
Pyeon
Youqi Zheng, Xunzhao Li, Hongchun Wu
Paul Bryce, Martin Knight, Chris Eatwell
Tuesday 10:10 AM - 12:15 PM
Reactor Analysis Methods I - Boiler
Chairs: Chang Ho LEE, Argonne National Laboratory and Guy MARLEAU, Ècole Polytechnique de
Montrèal
10:10
10:35
11:00
11:25
11:50
Determination of the Reflector Parameter Through Data Assimilation with the
COCAGNE Calculation Code Using a
TRIPOLI 4 Reference Simulation on KAIST
Benchmark
Multilevel Quasidiffusion Method with Multiplicative Corrections For Eigenvalue Neutron
Transport Problems
The IRSN ORION Project: Development of
New Capabilities for Neutronics Deterministic
Simulations Dedicated to Safety Analysis
Application of the Method of Manufactured Solutions to the 1D Sn Equation
Experiment Informed Neutron Transport
Model of TRIGA Irradiation Location
25
Jean-Philippe Argaud, Bertrand Bouriquet,
Ansar Calloo, Edgar Luis
Luke R. Cornejo, Dmitriy Y. Anistratov
Sophie Pignet, Franck Bernard, Vivian
Salino, Julien Taforeau, Alain Hebert, Antoine
Bruneau
Jipu Wang, William R. Martin, Benjamin S.
Collins
James B. Tompkins, Ryan G. McClarren
TUESDAY MORNING
Cross Section Methods for Reactor Analysis - Sawtooth
Chairs: Rachel SLAYBAUGH University of California, Berkeley and Eugene SHWAGERAUS, Cambridge
University
10:10
10:35
11:00
11:25
11:50
Use of a Line of Pincells to Refine Discontinuity Factors and Group Structure for MOX/UO2
Modelling in the Embedded Supercell Methodology
Students’ Resonance Broadening to Teaching
or “How To Improve Students’ Learning Using
Flipped Classrooms”
Embedded Self-Shielding Method Applied to
Doubly Heterogeneous Fully Ceramic MicroEncapsulated Fuels
Predictions of PWR Cores Using PARAGON2
Based on Ultra-Fine Energy Mesh Crosssections Library
Temperature and Temperature Reactivity
Feedback Sensitivity Calculations for the
Transient Reactor Test Facility (TREAT)
Martin Knight, Paul Bryce, Tom Taylor
Christophe Demaziere, Christian Stöhr, Tom
Adawi
Kang-Seog Kim, Jianwei Hu, Cole A. Gentry
Mohamed Ouisloumen
Dimitrios C. Kontogeorgakos, Heather M. Connaway, Dionissios D. Papadias, Arthur E.
Wright
Recent Developments in Monte Carlo Codes and Methods I - Columbine
Organized by: Jaakko LEPPÄNEN, VTT Technical Research Centre of Finland
Chairs: Benoit FORGET, Massachussetts Institute of Technology and Jaakko LEPPÄNEN, VTT Technical Research Centre of Finland
10:10
10:35
11:00
11:25
11:50
Approximate Mean Free Path Based Kernel
Density Estimators for Reaction Rates in Reactor Physics Problems
Integrated Decay Source Capability for LargeScale Monte Carlo Radiation Transport Calculations
Expanding the use of Serpent 2 to fusion applications: development of a plasma neutron
source
New Interpolation Capabilities for Thermal
Scattering Data in Serpent 2
Delayed Neutron Emission Model for Time Dependent Simulations with the Serpent 2 Monte
Carlo Code – First Results
26
Timothy P. Burke, Brian C. Kiedrowski, William
R. Martin
David P. Griesheimer, Stephen C. Marin, Paul
K. Romano, Mark H. Stedry
Paula Sirén, Jaakko I. Leppänen
Tuomas P. Viitanen, Jaakko I. Leppanen
Ville Henrikki Valtavirta, Mohammad Hessan,
Jaakko I. Leppanen
TUESDAY MORNING
Research and Test Reactors - Camas
Organized by: Mark DeHART, Idaho National Laboratory and Benoit DIONNE, Argonne National Laboratory
Chairs: Benoit DIONNE, Argonne National Laboratory and Luka SNOJ, Institut ”Jozef Stefan”
10:10
10:35
11:00
11:25
11:50
Core Design Studies for a Low-Enriched Uranium Reactor for Cold Neutron Source at NIST
Neutronic Analysis of Use of HANARO fuel in
WWR-SM Reactor
New As-Run Neutronics Analysis for RERTR12 Fuel Foil Experiments
Fast Spectrum Material’s Testing Reactor with
Variable Energy Spectra to Support Advanced
Reactors Program and Light Water Reactor
Sustainability Program R&D
Feasibility Investigation of Application of
MPACT to Core Design Studies of NBSR-2, a
Heavy Water Reflected, Heterogeneous LEU
Research Reactor
Zeyun Wu, Robert E. Williams
Lara Peguero, Todd Palmer
Margaret Marshall, Misti A. Lillo
Jonathan B. Scherr, Pavel V. Tsvetkov
Bryan D. Eyers
Sensitivity/Uncertainty Analysis III - Lupine
Chairs: Qiong ZHANG, Baker Hughes and Wei SHEN, Canadian Nuclear Safety Commission
10:10
10:35
11:00
11:25
11:50
Fission Product Yields Covariance Generation
Methodologies and Uncertainty Propagation
Using the URANIE Platform
A New Method for Removing Systematic Errors in Cross Section Adjustment for Accurate
Estimation of Minor-Actinide Transmutation in
Fast Reactors
Variance Reduction Factor Calculations for
Neutronics Parameters of Accelerator-Driven
System
Comparison of Fission Yield Perturbation
Methodologies on Nuclide Composition of a
PWR UO2 Fuel Assembly
Thermal-Hydraulic Uncertainty Propagation in
a Main Steam Line Break Scenario
27
Nicholas Terranova, Pascal Archier, Olivier
Serot, David Bernard, Cyrille De Saint Jean,
Marco Sumini
Toshikazu Takeda
Go Chiba, W.F.G. van Rooijen, T. Endo, C.H.
Pyeon
Olivier Leray, Luca Fiorito, Dimitri Rochman,
Hakim Ferroukhi, Andreas Pautz, A.
Stankovskiy, G. Van den Eynde
Emilio Castro Gonzalez, Maria Avramova, Diana Cuervo, Nuria Garcia Herranz
TUESDAY MORNING
Multi-Physics Reactor Simulations IV - Limelight C
Chairs: Scott PALMTAG Core Physics, Inc. and Ville VALTAVIRTA, VTT Technical Research Centre of
Finland
10:10
10:35
11:00
11:25
11:50
A Novel Tightly Coupled Method for Reactor
Transient Simulations
On Steady-State Multiphysics Stability and
Related In-Core Fuel Management Capabilities in DONJON5
Internal Coupling of the Code DYN3D with the
USNRC Code TRACE - First Results
Coupled Neutronics and Heat Transfer in Accident Tolerant Composite Matrix Nuclear Fuels
A Preconditioning Algorithm for JFNK Method
Applied to Multi-Physics Calculations
Jaron P. Senecal, Wei Ji
Vivian Salino, Alain Hebert
Jose Angel Gonzalez-Vargas, Victor Hugo
Sanchez, Javier Jimenez
Christopher G. Morrison, Wei Ji, Jaron P.
Senecal
Jianan Lu, Jiong Guo, Han Zhang, Fu Li
Advanced Multidimensional Reactor Kinetics Methods I - Ram
Organized by: Sedat GOLUOGLU, University of Florida, Gilles YOUINOU, Idaho National Laboratory
and Wilfred VAN ROOIJEN, University of Fukui
Chairs: Todd PALMER, Oregon State University and Wilfred VAN ROOIJEN, University of Fukui
10:10
10:35
11:00
11:25
11:50
Assessment of the CABRI Transients Power
Shape by Using CFD and Point Kinetics Codes
Operational Readiness of the Rattlesnake
Multidimensional Transport Code
Implementation of the Improved Quasi-Static
Method in Rattlesnake/MOOSE for TimeDependent Radiation Transport Modelling
Preparation of a Neutron Transport Data Set
for Simulations of the Transient Test Reactor
Facility
Research in Support of TREAT Kinetics Calculations Using Rattlesnake/BISON Coupling
Within MAMMOTH
28
Jean-Pascal Hudelot
Barry D. Ganapol, Mark D. DeHart, Frederick N. Gleicher, Abderaffi Ougouag, Javier Ortensi, Richard C. Martineau
Zachary M. Prince, Jean C. Ragusa, Yaqi
Wang
Javier Ortensi, Yaqi Wang, Benjamin A. Baker,
Sebastian Schunert, Frederick N. Gleicher,
Mark D. DeHart, Alexandre Laurier, Alain
Hebert
Mark D. DeHart, Javier Ortensi, Frederick N.
Gleicher, Yaqi Wang, Sebastian Schunert
TUESDAY AFTERNOON
Reactor Analysis Methods II - Boiler
Chairs: Florent Heidet, Argonne National Laboratory and Akio YAMAMOTO, Nagoya Univeristy
1:30
1:55
2:20
2:45
3:10
Leakage Correction of Homogenized FewGroup Constants through Functionalization on
Leakage Fraction
Comparison of 1-D/1-D Fusion and 1-D/1-D
Hybrid Methods in a Two-Dimensional Transport Problem: Numerical Results
Problem Formulation of Numerical Reactivity
Measurement Simulation
Development of Two-Step Reactor Physics
Analysis Procedure for Advanced High Temperature Reactors
Construction of Optimized Experimental Responses in Support of Model Validation via
Physics Coverage Mapping Methodology
Young Suk Ban, Han Gyu Joo
Seungsu Yuk, Nam Zin Cho
Nurbol Zhylmaganbetov, Sergey Shevchenko
Cole A. Gentry, G. Ivan Maldonado, KangSeog Kim
Dongli Huang, Hany S. Abdel-Khalik
Fast Reactors I - Camas
Chairs: Massimiliano FRATONI University of California, Berkeley and Bruno MERK, University of Liverpool/National Nuclear Laboratory
1:30
1:55
2:20
2:45
3:10
Fast Reactor Diagrid and Axial Expansion
Models for the Diffusion Equation
Calculation Methodology Assessment to Detect Localised Perturbation In Sodium-Cooled
Fast Reactors with Ex-Core Instrumentation
Monte Carlo Analysis Of SNEAK-12A Core
Disruption In Liquid-Metal Fast Breeder Reactors – the Path For Innovative Severe Accident
Studies In ZPR
Development of a Fast Reactor for Minor Actinides Transmutation - Improvement of Prediction Accuracy for MA-Related Integral Parameters based on Cross-section Adjustment
Technique
A Search for Theories Enabling Analyses of
Spatial Effects in Highly Coupled SFR Cores
29
Armin Seubert, Kiril Velkov
Vasudha Verma, Carl Hellesen, Christian
Jammes, Philippe Filliatre, Staffan Jacobsson
Svärd
Marat Margulis, Patrick Blaise, Erez Gilad
Kenji Yokoyama, Shuhei Maruyama, Kazuyuki
Numata, Makoto Ishikawa, Toshikazu Takeda
Maxence Maillot, Jean Tommasi, Gerald Rimpault
TUESDAY AFTERNOON
Depletion Methods III - Ram
Chairs: Rodolfo FERRER, Studsvik Scandpower and Dan KOTLYAR, University of Cambridge
1:30
1:55
2:20
2:45
3:10
Burnable Poison Designs for a Soluble-BoronFree Civil Nuclear Marine PWR Core
Validation of CASMO5 Gadolinium Depletion
Analysis
Evaluation of the Effect of Burn-Up on Neutron Flux and Reaction Rate Distributions in
the TRIGA Mark II Reactor
Solution of the BEAVRS Benchmark Using
CASMO-5 / SIMULATE-5 Code Sequence
High-Fidelity Heat Deposition Analysis for the
High Flux Isotope Reactor
Syed Bahauddin Alam, Benjamin A. Lindley,
Geoffrey T. Parks
Yusuke Kuroda, Tsuyoshi Ama, Takashi Yoshii
Žiga Štancar, Luka Snoj, Loic Barbot
Valentyn Bykov, Alexander Vasiliev, Hakim
Ferroukhi, Andreas Pautz
Eva E. Sunny, Benjamin Betzler, David Chandler, Germina Ilas
MCNP Validation and Applications - Sawtooth
Chairs: Forrest BROWN Los Alamos National Laboratory and Eric DUMONTEIL, Institut de Radioprotection et de Sûreté Nucléaire
1:30
1:55
2:20
2:45
3:10
Validating MCNP5 Libraries And Predicting
The Accuracy In Calculating The Effective Multiplication Factor (Keff) As A Function In Moderator To Fuel Ratios
Energy Deposition Prediction Calculations Using MC21 And MCNP for Calorimeters of Various Materials in the University of Wisconsin
Nuclear Reactor
An Analytic Benchmark of Neutron Free-Gas
Scattering Using Continuous-Energy Cross
Sections in MCNP6
Verification of Solid Body Geometries in
MCATK
Fission Neutron Multiplicity in MCNP6 Criticality Calculations
Karim Mahmoud Hossny
Edwin J. Grant, Laura Bartol, Timothy H. Trumbull, Paul P. Wilson, Robert J. Agasie, Wes
Culberson, Jeff Radkte, Edward Kent, Paul
Brooks, Mark H. Anderson
Matthew A. Gonzales, Anil K. Prinja, Forrest
B. Brown, Brian C. Kiedrowski
Travis J. Trahan, Jesse Giron, Jeremy E.
Sweezy
Mario I. Ortega, Michael E. Rising, Forrest B.
Brown, Anil K. Prinja
Validation Facilities - Lupine
Chairs: John BESS , Idaho National Laboratory and (TBD)
1:30
1:55
Serpent Stereolithography Modeling of the GIACINT Critical Assembly Experimental Facility
Development of a Verification Benchmark
Suite for the ATR Reactor Physics Upgrade
30
Alberto Talamo, et al.
Barry D. Ganapol, Dave W. Nigg
TUESDAY AFTERNOON
2:20
2:45
3:10
FFTF Passive Safety Test Data for Benchmarks for New LMR Designs
Verification Methodology and Procedure of
JSNT-S
The 2D Static Benchmark Calculations for the
SAFARI-1 Research Reactor Core Characterisation
David W. Wootan, A. M. Casella
Guang Chun Zhang, Tangpei Cheng, Yuang
Guang Fu, Deng Li
Lesego Ernest Moloko, Julien Politello,
Jacques Di Salvo, Corinne D’Aletto
Multi-Physics Reactor Simulations V - Limelight C
Chairs: Wei JI, Rensselaer Polytechnic Institute and Ville VALTAVIRTA, VTT Technical Research Centre
of Finland
1:30
1:55
2:20
2:45
3:10
Cross Section Homogenization Technique for
Transient Calculations
Studsvik’s Tools for the Analysis of Reactivity
Transients
IAEA CRP on HTGR Uncertainties: Comparison of Ex. I-2c Nominal Results and Coupling
with the PHISICS/RELAP5-3D Core Model for
Ex. II-1
Development of Multiphysics Tools for
Fluoride-Cooled High Temperature Reactors
Enhanced Fidelity Depletion for Molten Salt
Reactors
Kevin Dugan, Igor Zmijarevic,
Sanchez
Gerardo M. Grandi, Jerry L. Judd
Richard
Pascal Nicolas Rouxelin, Gerhard Strydom,
Kostadin N. Ivanov
Manuele Aufiero, Massimiliano Fratoni
Daniel Wooten, Massimiliano Fratoni
Nuclear Data, Evaluations & Libraries III - Columbine
Chairs: Yuxuan LIU, University of Michigan and (TBD)
1:30
1:55
2:20
2:45
3:10
On Methods for Conversion to Multipole Formalism
Verification of the On-the-Fly Thermal Scattering Sampling Method for Bound Hydrogen in
Light Water
Neutron Data Adjustment Based on Integral
Critical Experiments on the BFS-Facility With
Different Neutron Spectrum
Multigroup Data Processing for the Embedded
Self-Shielding Method in SCALE
First Principles Molecular Dynamics Implementation in Thermal Neutron Scattering Analysis
31
Pablo P. Ducru, Vladimir Sobes, Benoit Forget,
Kord S. Smith
Andrew T. Pavlou, Wei Ji, Forrest B. Brown
Olga Nikolaevna Andrianova, Gleb Borisovich
Lomakov, Vladimir Nikolaevich Koscheev,
Gennady Nikolaevich Manturov
Mark L. Williams, Dorothea Wiarda, KangSeog Kim, Matthew A. Jessee
J. L. Wormald, A. Singhal, A. A. Petersen, Ayman I. Hawari
TUESDAY AFTERNOON
Fuel Cycle Physics, Management & Optimization III - Boiler
Organized by: Geoff Parks, Cambridge University and Temitope Taiwo, Argonne National Laboratory
Chairs: Jorge NAVARRO, Idaho National Laboratory and Liangzhi CAO, Xi’an Jiaotong University
4:00
4:25
4:50
5:15
Fuel Cycle Analysis of Multi-batch Operation
of a Denatured Molten Salt Reactor
Generation of Cross Sections for Use in Transition Analysis Using ORION
Portable Reactor Data Library Interpolation
Via Self-describing ORIGEN Libraries
Integrated Software Tools for Radiation Damage, Activation and Transmutation Studies in
Advanced Nuclear Systems
Kien Ngoc Trinh, Geoffrey T. Parks, Dan Kotlyar, Carlo Fiorina
Joshua L. Peterson, Andrew Worrall, Eva E.
Sunny, William Wieselquist, Robert Gregg
Nicholas C. Sly, Steve Eugene Skutnik,
William Wieselquist
Ilya Sergeevich Kuptsov, Andrei Andrianov,
Yury Korovin, Artem Dogov, Leonid Svetlichnyy
Reactor Analysis Methods III - Sawtooth
Chairs: Chang Ho LEE, Argonne National Laboratory and Evgeny IVANOV, Institut de Radioprotection
et de Sûreté Nucléaire
4:00
4:25
4:50
5:15
Pin-by-Pin Reactor Core Analysis Based on
a NEM-based Two-level Hybrid CMFD Algorithm
Coupling Sjöstrand and Feynman Methods in
Prompt Neutron Decay Constant Analyses
Key Neutronic Parameter for Commissioning
Reactor
APOLLO3®: CEA/DEN Deterministic MultiPurpose Code for Reactor Physics Analysis
Seongho Song, HwanYeal Yu, Yonghee Kim
Alberto Talamo, et al.
Laurent CHABERT, Eric Duchemin, Clement
Huot-Marchand, Particia Sireta
Didier Schneider, Florence Dolci, Franck
Gabriel, Jean-Marc Palau, Matthieu Guillo,
Baptiste Pothet
Transient Reactor Testing II - Ram
Organized by: Javier ORTENSI and Dan WACHS, Idaho National Laboratory
Chairs: Javier ORTENSI, Idaho National Laboratory and Ronald Ellis, Oak Ridge National Laboratory
4:00
4:25
CABRI Facility: Upgrade, Refurbishment,
Recommissioning and Experimental Capacities
TREAT Multi-SERTTA Neutronics Design and
Analysis Support
4:50
Treat Irradiation Vehicle Designs, Capabilities,
and Future Plans
5:15
Calculation of the TREAT Minimum Critical
Core with MAMMOTH and Serpent
32
Jean-Pascal Hudelot
John D. Bess, Nicolas E. Woolstenhulme,
Connie M. Hill, Robert C. O’Brien, Samuel E.
Bays
Nicolas E. Woolstenhulme, John D. Bess, C.B.
B. Davis, G.K. Housley, C.B. B. Jensen, R.C.
C. O’Brien, D.M. Michael Wachs
Anthony Lewis Alberti, Todd S. Palmer, Javier
Ortensi, Mark David DeHart
TUESDAY AFTERNOON
Sub-critical systems II - Camas
Chairs: Thomas SUTTON, Knolls Atomic Power Laboratory and Imre PAZSIT, Chalmers University
4:00
4:25
4:50
Reactivity Measurements in Subcritical Systems
Analysis and Burnup Modeling of the
GEM*STAR Accelerator-Driven System
Analysis of the External Source Modeling in a
Subcritical Reactor
Leticia Negrao Pinto, Adimir dos Santos, Eduardo Gonnelli
William J. Walters, Alireza Haghighat, Bruce
Vogelaar, Katherine K. Royston
Zafar Iqbal Zafar, Myung Hyun Kim
Sensitivity/Uncertainty Analysis IV - Lupine
Chairs: Hany ABDEL-KHALIK, Purdue University and Hyung Jin SHIM, Seoul National University
4:00
4:25
4:50
5:15
Quantification of the SCALE 6.1 Eigenvalue
Uncertainty Due to Cross-Section Uncertainties for Exercise I-1 of the IAEA CRP on HTGR
Uncertainties.
Uncertainty Analysis of Assembly and
Core-Level Calculations with Application to
CASMO-4 and SIMULATE-3
IAEA Coordinated Research Program on
HTGR Uncertainty Analysis: Results of Exercise I-1 Model and the Application of the RPT
Method
Direct Evaluation of Nuclear Data Uncertainty
Propagation in Pebble-Bed HTR Core
Vishnu Visvanathan Naicker, D Maretele, F
Reitsma, F Bostelmann, G Strydom
Maria Pusa
Wonkyeong Kim, Frederik Reitsma, Deokjung
Lee
Lidong Wang, Jiong Guo, Fu Li, Chen Hao,
Kostadin N. Ivanov, Pascal Nicolas Rouxelin
Advanced Multidimensional Reactor Kinetics Methods II - Limelight C
Organized by: Sedat GOLUOGLU, University of Florida, Gilles YOUINOU, Idaho National Laboratory
and Wilfred VAN ROOIJEN, University of Fukui
Chairs: Sedat GOLUOGLU, University of Florida and Wilfred VAN ROOIJEN, University of Fukui
4:00
4:25
4:50
5:15
Development of Kinetic Model for MHI Lattice
Physics Code
Calculation and Research of Neutron TimeSpatial Kinetics on Accelerator Driven SubCritical System
Models and Methods for the Representation
of Decay and Photon Heat in Spatial Kinetics
Calculations
Application
of
TDKENO
to
TREAT
Temperature-Limited Transients
33
Yohei Kamiyama, Kazuki Kirimura, Kazuya
Yamaji, Shinya Kosaka, Hiroki Koike
Xu Li, Yu Hong, Hu Yun, Wang Xinzhe
Dominic Caron, Sandra Dulla, Piero Ravetto,
Laura Savoldi, Roberto Zanino
Justin Paluch, Dustin R. Popp, Hannah Morbach, Victoria Graham, Mark David Dehart,
Sean Morell, Sedat Goluoglu
WEDNESDAY MORNING
Nuclear Data, Evaluations & Libraries IV - Columbine
Chairs: Rachel SLAYBAUGH University of California, Berkeley and (TBD)
4:00
4:25
4:50
5:15
Importance of the Neutron Flux Information
to the Evaluation of Thermal Neutron Capture
Cross Section and Resonance Integral of Minor Actinides
Parameterized Representation of Macroscopic Cross Section in Burn-Up Cycles
Investigation of Fast Neutron Induced Fission
of 238U: Theory and Experiments
The Fast Neutron Induced Fission Cross Section of 240, 242Pu
Kazuhito Mizuyama, Nobuyuki Iwamoto, Osamu Iwamoto
Thiago Freitas Belo, João Claudio B. Fiel
F.-J. Hambsch, A. Tudora, D.L. Duke, F.
Tovesson
F.-J. Hambsch, P. Salvador Castiñeira, S.
Oberstedt, A Göök, M. Vidali
Wednesday 8:00-9:40 AM
Fuel Cycle Physics, Management & Optimization IV - Boiler
Organized by: Geoff Parks, Cambridge University and Temitope Taiwo, Argonne National Laboratory
Chairs: Fausto FRANCESCHINI, Westinghouse Electric Company and Erez GILAD, Ben-Gurion University of the Negev
8:00
8:25
8:50
9:15
High Conversion Th-U Fuel Cycle for Current
Generation of PWRs
Fuel Cycle Analysis Using Bright-lite in the Cyclus Simulator
HCSMR Fuel Assembly Optimization with
APOLLO2 and URANIE CODES
Helium Generation Within Reactor Internal
Components of Fluence Benchmark Models
Using Coupled RAMA-SCALE
34
Daniela Baldova, Emil Fridman, Eugene
Shwageraus
Cem Bagdatlioglu, Robert R. Flanagan, Erich
A. Schneider
Denis Janin, Michel Soldevila, Siegfried
Douce, Marcus Seidl, Gilles Arnaud, Frederic
Damian, Christine Poinot, Rafael Macian-Juan
Ethan C. Taber, Victor G. Smith, Eric N. Jones
WEDNESDAY MORNING
Reactor Dosimetry - Camas
Chairs: John BESS , Idaho National Laboratory and Tuomas VIITANEN, VTT Technical Research Centre
of Finland
8:00
8:25
8:50
9:15
CASMO-5 Analysis of Reactivity Worths of
Burnt PWR Fuel Samples Measured in LWRPROTEUS Phase II
Interpretation of Local Flux Measurements for
Reactivity Prediction
Developing a Fast Neutron Beam Capability
in MASURCA: Spectrum and Intensity Evaluation
Benchmarking of Fission and Activation Rate
in VVER-1000 Mock-Up in LR-0 Reactor
Peter Grimm, Mathieu Hursin, Gregory Perret,
Daniel Siefman, Hakim Ferroukhi
Sandra Dulla, Siew Sin Hoh, Piero Ravetto,
Paolo Saracco
Marco Sumini, Luca Dioni, Brian Stout, Robert
P. Jacqmin
Michal Kostal, Vojtech Rypar, Evzen Losa,
Martin Schulc, Davit Harutunyan, Marie
Svadlenkova, Jan Milcak, Michal Sunka
Full Core Analysis Methods II - Columbine
Chairs: Zain KARRIEM, Idaho National Laboratory and Sophie PIGNET, Institut de Radioprotection et
de Sûreté Nucléaire
8:00
8:25
8:50
9:15
Reproduction of a Power Azimuthal Disbalance Using Data Assimilation: Application to
Twin Experiments
First Evidence of the Pivotal Motion (Tilting
Mode) of The Core Barrel in the Ringhals-4
PWR
Development of Generic Inserts Methodology
Rod Internal Pressure Quantification and Distribution Analysis Using FRAPCON
Coline Brosselard, Bertrand Bouriquet,
Matthieu De Sequeira, Hadrien Leroyer,
David Couyras, Jean-Philippe Argaud
Cristina Montalvo, Imre Pazsit, Henrik Nylén,
Victor Dykin
Baocheng Zhang, Brian R. Coulter, Boyan D.
Ivanov
Ryan Bratton, Matthew A. Jessee, William
Wieselquist, Kostadin N. Ivanov
Experiments III - Sawtooth
Chairs: David NIGG, Idaho National Laboratory and Laurent CHABERT, AREVA-France
8:00
8:25
Research of Radioactive Properties of
Geopolymers Carried Out at the LVR-15
Nuclear Research Reactor
A Scrutinized Analysis on the Power Reactivity
Loss Measurement in MONJU
35
Zdena Lahodova, Ladislav Viererbl, Michal
Koleska, Tomas Cernousek, Zbynek Cerny
Hiroshi Taninaka, Yasufumi Kishimoto, Tetsuya Mouri, Shin Usami
WEDNESDAY MORNING
8:50
Analysis of Material Buckling Experiments
Performed in the MASCURA Facility in Support of the Astrid SFR Prototype Core Balance
Gerald Rimpault, Paul Dufay, Virginie Huy
Advanced and Small Modular Reactor Designs I - Limelight C
Chairs: Massimiliano FRATONI University of California, Berkeley, and Frederik REITSMA, International
Atomic Energy Agency
8:00
8:25
8:50
9:15
Coupled Neutronic-Thermal-Hydraulic Analysis of a Small FHR Core with Pin-Type Fuel
Assemblies
Preliminary Design of Boron-Free Small Modular Pressurized Water Reactor
Benchmark Calculations of the MHTGR-350
MW Core using Explicit Modeling Approach of
RMC
Impact of Control Rod Position and Homogenization on Sodium Void Effect in CFV-Type
SFR
Hassan Mohamed, Dan Kotlyar, Geoffrey
Thomas Parks, Yaniv Shaposhnik
Jiwon Choe, Deokjung Lee, Ho Cheol Shin
Shichang Liu, Zhen-an Wang, Ding She, Jingang Liang, Kan Wang
Mikael Erik Andersson, David Blanchet, Henrik Nylén, Robert P. Jacqmin
Validation of Kinetics Methods - Ram
Chairs: Zeyun WU, National Institute of Standards and Technology and (TBD)
8:00
8:25
8:50
9:15
Validation of a RELAP5-3d Point Kinetics
Model of TREAT
Control Rod Insertion Method Analysis - Dynamic vs. Static Reactivity
The Determination of Reflector Kinetic Parameters Through Rossi-Alpha Experiments in the
IPEN/MB-01 Reactor
Verification of the Time-dependent Transport
Code TDKENO with the Monte Carlo Code
KENO-VI
36
Cliff B. Davis, Nicolas Eric Woolstenhulme
Vid Merljak, Marjan Kromar, Luka Snoj, Andrej
Trkov
Eduardo Gonnelli, Leticia Negrao Pinto,
Adimir dos Santos, Ricardo Diniz
Zander Mausolff, Mark D. DeHart, Sedat Goluoglu
WEDNESDAY MORNING
Validation of Thermal/Hydraulic Methods - Lupine
Chairs: Hongbin ZHANG Idaho National Laboratory and Fabrizio GABRIELLI, Karlsruhe Institute of Technology
8:00
8:25
8:50
9:15
A first approach of TAPIRO ThermalHydraulics Definition Model, by RELAP
and TIESTE-MINOSSE Codes. Reactivity
and Mass Flow Rate Transient Analysis
Validation of the HEM and Moody Critical Flow
Models in POLCA-T
Phase II of the EBR-II SHRT-45R Benchmark
Study - TerraPower’s SAS4A/SASSYS-1 Results
Neutronics/Fuel Thermomechanics Coupling
in the Framework of a REA (Rod Ejection Accident) Transient Scenario Calculation
Giancarlo Bianchini, Mario Carta, Valentina
Fabrizio, Orlando Fiorani, Carlo Parisi, Alfonso
Santagata
Milan Tesinsky, Jonathan Wang, Ulf Bredolt
Ethan A. Bates, Bao Truong, Lakshana R.
Huddar
Jean-Charles Le Pallec,
Nkonga, Nicolas Crouzet
Katherine Mer-
Wednesday 10:10 AM-12:15 PM
Reactor Analysis Methods IV - Boiler
Chairs: Zeyun WU, National Institute of Standards and Technology and Yunzhao LI, Xi’an Jiaotong
University
10:10
10:35
11:00
11:25
11:50
On Using Grasshopper Add-On for CAD to
MCNP Conversion
Implementation of Coarse-Mesh Nonlinear
Diffusion Acceleration for Hexagonal Geometry in CASMO5
KMacs, a Modular Adaptable Core Simulator
Fourier Analysis of Iteration Schemes for KEigenvalue Transport Problems with FluxDependent Cross Sections
Error Due to Angular Discretization in the Discrete Ordinates Approximation of the Transport Equation in Two-Dimensional Cartesian
Geometry
37
Bor Kos, Luka Snoj
Rodolfo M. Ferrer, Lulu Li, Joel D. Rhodes
Matias Zilly, Matthias Kuentzel, Alexander Aures, Volker Hannstein, Kiril Velkov, Andreas
Pautz
Brendan M. Kochunas, Edward W. Larsen
Xiaoyu Hu, Yousry Y. Azmy, Camila B. Picoloto, Anderson Tres, Liliane B. Barichello
WEDNESDAY MORNING
Burn-up Credit and Spent Fuel Measurements - Limelight C
Organized by: Dale LANCASTER, NuclearConsultants.com and Mark DeHART Idaho National Laboratory
”Chairs: John WAGNER, Idaho National Laboratory and Jean-Christophe SUBLET, United Kingdom
Atomic Energy Authority”
10:10
10:35
11:00
11:25
11:50
Validation of Monte Carlo Burnup Calculation
for Thai Research Reactor
Dose Rate Analysis in a High Capacity Nuclear
Spent Fuel Storage System using the MAVRIC
Code
Validation of WIMS/PANTHER PWR Fuel Reactivity Depletion using the BEAVRS Benchmark Flux Map Data
Study on the Impacts of Burn-up Measurement
Errors on the Discharge Burn-up Distribution of
PB-HTR
Effects of Control Blade History, Axial Coolant
Density Profiles, and Axial Burnup Profiles on
BWR Burnup Credit
Chanatip Tippayakul, Somkit Chowchanglag
Agustin Abarca, Alvaro Bernal, Rafael Miro,
Gumersindo Verdu
Reece Daniel Harrison, Gareth Startin, Ben
Lindley, David Powney, Geoff Parks, Paul Hutt
Bing Xia, Jiong Guo, Fu Li
Brian J. Ade, William J. Marshall, Stephen M.
Bowman, Jesus S. Martinez Gonzalez
Recent Developments in Monte Carlo Codes and Methods II - Columbine
Chairs: Alireza HAGHIGHAT, Virginia Polytechnic Institute and Zhang PENG, Ulsan National Institute of
Science and Technology
10:10
10:35
11:00
11:25
11:50
Expanding the Use of Serpent 2 to Fusion Applications: Shut-Down Dose Rate Calculations
Monte Carlo Sensitivity and Uncertainty Calculations with Continuous-Energy Nuclear Covariance Data
Testing Advanced Methods For Sensitivity/Uncertainty Analysis in the Monte Carlo
Code Serpent
MCNP6 GENXS Option Expansion to Include
Fragment Spectra of Heavy Ions
A Cumulative Migration Method for Computing
Rigorous Transport Cross Sections and Diffusion Coefficients for LWR Lattices with Monte
Carlo
38
Jaakko I. Leppanen, Toni Kaltiaisenaho
Dong Hyuk Lee, Hyungjin Shim, Chang Hyo
Kim
Manuele Aufiero, Massimiliano Fratoni
Leslie Kerby, Stepan G. Mashnik, Jeffrey S.
Bull
Zhaoyuan Liu, Kord S. Smith, Benoit Forget
WEDNESDAY MORNING
Verification and Validation of Reactor Analysis Methods II - Sawtooth
Chairs: Wei JI, Rensselaer Polytechnic Institute and Wei SHEN, Canadian Nuclear Safety Commission
10:10
10:35
11:00
11:25
11:50
Benchmark Progress Towards TREAT M8CAL
Core Loading to Support Validation of TREAT
Operations
Analysis of the MIT BEAVRS Benchmark Using the DRAGON5/PARCS Code Sequence
OPAL Reactor Calculations using Reactor
Physics Code Serpent
Validation and Verification of the MPACT Code
Lessons Learned from a VVER Benchmark
Modeling
John D. Bess, Benjamin Chase, James Parry
Julien Taforeau, Vivian Salino
Lance Maul, George Braoudakis, Mark Ho,
Guan Heng Yeoh
Thomas J. Downar, Brendan M. Kochunas,
Benjamin Collins
Ondrej Novak, Ondrej Chvala
Modeling and Simulation for Nonproliferation and Safeguards - Camas
Organized by: Sean MORREL,L Idaho National Laboratory and Todd PALMER, Oregon State University
Chairs: Sean MORRELL, Idaho National Laboratory and and Silva KALCHEVA, Studiecentrum voor
Kernenergie/Centre d’Étude de l’énergie Nucléaire (SCK-CEN)
10:10
10:35
11:00
11:25
11:50
New Model for Parametric Analysis of Fuel Debris Criticality
Using Cherenkov Light to Quantify Reactor Kinetics Parameters and Infer Fissile Material Inventory for Nuclear Nonproliferation
Development of a Scintillator Detector Response Post Processing Tool for MCNP Output
A Generalized Method for Fissile Mass Characterization using Short-Lived Fission Product
Gamma Measurements
Advanced Tools Based on a Multiple Objective Framework for Proliferation Risk and Resistance Assessments
Marc Ernoult, Kotaro Tonoike
Thomas V. Holschuh, Wade R. Marcum, David
L. Chichester, Scott M. Watson, Sean R. Morrell
M. T. Andrews, C. R. Bates, E. A. McKigney,
C. J. Solomon, A. Sood
Justin R. Knowles, Steve Eugene Skutnik,
David Glasgow, Roger Kapsimalis
Ilya Sergeevich Kuptsov, Andrey A. Andrianov
SCALE Validation - Lupine
Chairs: Benoit DIONNE, Argonne National Laboratory and Friederike BOSTELMANN, Gesellschaft für
Anlagen- und Reaktorsicherheit (GRS)
10:10
10:35
Verification and Validation of New Unmodified
SCALE PWR Lattice Templates
Use of Polaris and PARCS to Predict Cycle
Depletion for Three Mile Island Unit One Cycles One and Two
39
Nathan T. Shoman, Steven E Skutnik
Peter Yarsky
WEDNESDAY AFTERNOON
11:00
11:25
11:50
Validation of Polaris, PARCS, and TRACE
Against DIMPLE S01a Benchmark
Neutronic Analysis of the APR1400 Reactor with SCALE and Serpent Reactor Physics
Codes - Power Distribution
Validation of Polaris and PARCS Against Otto
Hahn Second Core Zero Power Experiment
Benchmark
Peter Yarsky, Carl Thurston
Mohamed A. Elsawi, Zainab Alnoamani
Peter Yarsky, Raymond Skarda, Thomas
Boyle
Advanced and Small Modular Reactor Designs II - Ram
Chairs: Renae LENHOF, NuScale Power and Frederik REITSMA, International Atomic Energy Agency
10:10
10:35
11:00
11:25
11:50
New Small Long-Cycle PWR Core using Particle Burnable Poisons for Boron-Free Operation
Evaluation of the Safety and Breeding Performance of a Heterogeneous Fuel Assembly Design for a Metal Fueled SFR
A Molten Salt Reactor Study for the Transmutation of all German Transuranium in the
Frame of the Nuclear Phase Out
Lattice Physics Sensitivity Studies for
Thorium-Based Fuels in Pressure Tube
Heavy Water Reactors
Analysis of Reverse Flow Restriction Device
to Prevent Fuel Dryout During Boiling Water
Reactor Instability
Hoseong Yoo, Ser Gi Hong, Dae hee hwang,
Ho Cheol Shin
Bruno Rudi Merk, K. Devan, A. Bachchan, D.
Paul, P. Puthiyavinayagam, G. Srinivasan
Bruno Rudi Merk, Litskevich Dzianis
Blair P. Bromley, Owen Collins, Ashlea Colton
Majdi Ibrahim Radaideh, Tomasz Kozlowski,
Yousef M. Farawila
Reactor Analysis Methods V - Limelight C
Chairs: Sonat SEN, Idaho National Laboratory and Frederik REITSMA, International Atomic Energy
Agency
1:30
1:55
2:20
2:45
3:10
A New Stochastic Acceleration Scheme for the
Monte Carlo Method
On the Characteristics of Transfer Matrix of
Generalized Modified Power Method
Improved Resonance Self-Shielding Method
Considering Resonance Scattering Effect
On the Iterative Convergence of the Integral
Transport Matrix Method in Two-Dimensional
Geometry for the Diamond Difference Method
Acceleration of Discrete Ordinates Calculations using Parallel Partial Current Rebalance
Algorithm and Algebraic Multigrid Solver
40
Inhyung Kim, Yonghee Kim
Peng Zhang, Hyunsuk Lee, Deokjung Lee
Sooyoung Choi, Changho Lee, Deokjung Lee
Dylan Hoagland, Yousry Y. Azmy, R. Joseph
Zerr
Tangpei Cheng, Zeyao Mo, Junxia Wei,
Guangchun Zhang, Huayun Shen, Li Deng
WEDNESDAY AFTERNOON
Fast Reactors II - Camas
Chairs: Florent HEIDET, Argonne National Laboratory and Valentyn BYKOV, École Polytechnique
Fédérale de Lausanne
1:30
1:55
2:20
2:45
3:10
Passive Safety Characteristics of Stationary
Liquid Fuel Fast Reactor (SLFFR)
Development of the DARWIN3-SFR Fuel Cycle Tool for Decay Heat Calculations in New
Generation Fast Reactors
Long-Life Small Modular Sodium-Cooled Fast
Reactor Core Design with Breed-And-Burn
Strategy
Impact of Energy Capacity Growth on Continuous Recycle Fuel Cycles Based on Fast Critical Reactors
Axial Fuel Rod Expansion Model in Nodal
Code DYN3D for SFR Application
Tian Jing, Yeon Sang Jung, Won Sik Yang
Claire Vaglio-Gaudard, Pierre Bellier, Laurent Buiron, Sebastien Lahaye, Jean-Francois
Lebrat, Philippe Miranda, Benedicte Roque,
Aime Tsilanizara
Jinsu Park, Taewoo Tak, Jiwon Choe, Yongjin
Jeong, Deokjung Lee, T. K. Kim
Florent HEIDET, Taek Kyum Kim, Temitope A.
Taiwo
Evgeny Nikitin, Emil Fridman
Verification and Validation of Reactor Analysis Methods III - Columbine
Chairs: Brendan KOCHUNAS, University of Michigan and Piero RAVETTO, Politecnico di Torino
1:30
1:55
2:20
2:45
3:10
Reactor Physics Benchmark Suite Development for Nuclear Analysis Codes and Methods
Validations in Traveling Wave Reactor Applications
Validation of Decay Heat Evaluation Method
Based on FPGS Code for Fast Reactor Spent
MOX Fuels
Neutronic Assessment of TRISO Particle Fuels in a Small Fluoride Salt-Cooled HighTemperature Reactor
Validation of MOSRA-SRAC for Burnup of a
BWR Fuel Assembly
Verification and Validation of the Tetrahedral
Grid Radiation Transport Code THOR Based
on the Advanced Test Reactor Benchmark
41
Zhiwen Xu, Mark S. Onufer, Nicholas W.
Touran
Shin Usami, Yasufumi Kishimoto, Hiroshi Taninaka, Shigetaka Maeda
Hassan Mohamed, Benjamin Andrew Lindley,
Geoffrey Thomas Parks, Jaakko I. Leppanen
Kensuke Kojima
Raffi A. Yessayan,
Yousry Y. Azmy
Sebastian Schunert,
WEDNESDAY AFTERNOON
Recent Developments in Monte Carlo Codes and Methods III - Sawtooth
Chairs: David GRIESHEIMER, Bettis Atomic Power Laboratory and Jaakko LEPPÄNEN, VTT Technical
Research Centre of Finland
10:10
10:35
11:00
11:25
11:40
Improved Weight Window Variance Reduction
for Coupled Radiation Monte Carlo Transport
Calculations
The Mutual Information of the Fission Source
in Eigenvalue Calculations
Equipping OpenMC for the Big Data Era
Using Normality Tests to Assess the Validity of
Monte Carlo Confidence Intervals
Recent Advancements of Reactor Monte Carlo
Code RMC
David P. Griesheimer, Brian Robert Nease
Brian C. Kiedrowski, Charles D. Corbin
William R. Boyd, Paul Romano, Sterling
Harper
Thomas M. Sutton, Jason Haverkamp
Kan Wang, Jingang Liang, Shichang Liu, Xiaotong Shang, Xiao Fan, Yi Shu Qiu, Feng Yang,
Qicang Shen, Ganglin Yu
Finite Element Methods for Reactor Analysis - Boiler
Chairs: Sebastian SCHUNERT, Idaho National Laboratory and Liliane BARICHELLO, Universidade Federal do Rio Grande do Sul
1:30
1:55
2:20
2:45
3:10
A Flexible Nonlinear Diffusion Acceleration
Method for the First Order Eigenvalue Sn
Equations Discretized with Discontinuous
FEM
Least-Squares PN Formulation of the Transport Equation Using Self-Adjoint-Angular-Flux
Consistent Boundary Conditions
Asymptotic Preserving Least Square PN Methods of Transport Equation
Hybrid Pn-Sn Calculations with SAAF for the
Multiscale Transport Capability in Rattlesnake
Comparisons of the Finite-Element-withDiscontiguous-Support Method to ContinuousEnergy Monte Carlo for Pin-cell Problems
Sebastian Schunert, Yaqi Wang, Javier Ortensi, Frederick N. Gleicher, Benjamin A.
Baker, Mark D. DeHart, Richard C. Martineau
Vincent Laboure, Yaqi Wang, Mark D. DeHart
Weixiong Zheng, Ryan G. McClarren
Sebastian Schunert, Yaqi Wang, Mark D. DeHart, Richard C. Martineau
Andrew T. Till, Milan Hanus, Jijie Lou, Jim E.
Morel, Marvin L. Adams
Sensitivity/Uncertainty Analysis V - Lupine
Chairs: Andrea ALFONSI, Idaho National Laboratory and Maria PUSA, VTT Technical Research Centre
of Finland
1:30
Impact of Nuclear Data Uncertainties on the
Performance of the Advanced Burner Reactor
42
Nicolas E. Stauff, J. Shi, G. Aliberti, T. S. Sumner, K. Ivanov, T. K. Kim
WEDNESDAY AFTERNOON
1:55
2:20
2:45
3:10
The Contribution of Cross-section Uncertainties to Pebble Bed Reactor Eigenvalues Results: IAEA Cooperative Research project
Phase I Standalone Neutronics
The Bumpy Road to Code Validation Including
Correlations
A Perturbation Analysis Scheme in WIMS Using Transport Theory Flux Solutions
OECD/NEA Intercomparison of Deterministic and Monte Carlo Cross-Section Sensitivity
Codes Using SNEAK-7 Benchmarks
Frederik Reitsma, Wonkyeong Kim
Elisabeth Peters, Maik Stuke, Fabian Sommer
Glynn Hosking, Tim Newton, Peter Smith,
Richard Hiles, Ben Lindley
Ivan Alexander Kodeli, Victor Mastrangelo,
Evgeny A. Ivanov, Alexander Aures, Winfried Zwermann, Manuele Aufiero, Yannick
Peneliau, Kostadin N. Ivanov, Enrico Sartori
Advanced and Small Modular Reactor Designs III - Ram
Chairs: Renae LENHOF, NuScale Power and Ronald Ellis, Oak Ridge National Laboratory
1:30
1:55
2:20
2:45
3:10
In-Core Fuel Management Optimization for
Breed-and-Burn Reactors with 3D Fuel Shuffling
Analysis of the Coolant Density Reactivity Coefficient in LFRS And SFRS via Monte Carlo
Perturbation/Sensitivity
Hot Assembly and Whole-Core ThermalHydraulic Analysis of a High Power Density Marine Core with Neutronic/ThermalHydraulic Coupling
Neutronic Performance of High Power Density Marine Propulsion Cores using UO2 and
Micro-Heterogeneous THO2-UO2 Duplex Fuels
Fully Ceramic Microencapsulated Fuel for
Space Reactor Applications
Jia Hou, Staffan A. Qvist, Ehud Greenspan,
Roger Kellogg
Manuele Aufiero, Michael V. Martin, Massimiliano Fratoni, Emil Fridman, Stefano Lorenzi
Syed Bahauddin Alam, Geoffrey T. Parks,
Benjamin A. Lindley
Syed Bahauddin Bahauddin Alam, Benjamin
A. Lindley, Geoffrey T. Parks
Benjamin R. Betzler, Jeffrey Powers
Full Core Analysis Methods III - Boiler
Chairs: Benjamin CHASE, Idaho National Laboratory and Wei SHEN, Canadian Nuclear Safety Commission
4:00
4:25
4:50
High Flux Isotope Reactor Core Analysis
- Challenges and Recent Enhancements in
Modeling and Simulation
Investigation of the Bias Coming from Spectrum Corrections in the Simulations of Nuclear
Reactor Transients
Void Reactivity (Cmn) Coefficients as Indicators of Boiling Water Reactor Stability
43
Germina Ilas, Benjamin R. Betzler, David
Chandler, Eva E. Sunny
Christophe Demaziere
Victor Dykin, Christophe Demaziere
WEDNESDAY AFTERNOON
5:15
Development of Hodoscope-Reactor Core
Model for TREAT Transient Testing
Logan M. Scott, Samuel E. Bays
Multi-Physics Reactor Simulations VI - Limelight C
Chairs: Manuele AUFIERO, University of California, Berkeley and Christophe DEMAZIÈRE, Chalmers
University
4:00
4:25
4:50
5:15
Stability and Near-Optimal Underrelaxation of
Coupled Reactor Physics Calculations
Assessment of Pellet-Clad Interaction Indicators in Watts Bar Unit 1 Using VERA
Assessment of Thermal Hydraulic Feedback
Models
Analysis of Large Core Neutronics by the
Monte Carlo Method Coupled with Thermal
Hydraulics
Justin M. Pounders
Shane Stimpson, Jeffrey Powers, Kevin T.
Clarno, Roger P. Pawlowski, Ryan Bratton
Aaron M. Graham, Benjamin S. Collins, Robert
Salko, Scott Palmtag, Thomas J. Downar
Nicole Simone Guilliard, W. Bernnat, J. Lapins,
W. Zwermann, I. Pasichnyk, Y. Perin, K. Velkov
Reactor Operation and Control - Sawtooth
Organized by: Katherin GOLUOGLU, Syzygy Solutions and Akira TOKUHIRO, Purdue University
Chairs: Yousry GOHAR, Argonne National Laboratory and (TBD)
4:00
4:25
4:50
5:15
On-Line Monitoring Analysis of BEAVRS
Benchmark using NECP-ONION
Dead Time Corrections using the Backward
Extrapolation Technique
Self-Monitoring Fission Chamber: Theoretical
Groundwork
Development of Reactor Control Algorithm for
Thai Research Reactor
Zhuo LI, Hongchun Wu, Liangzhi Cao, Chao
Tian, Dingyong Chen
Chen Dubi, Benoit Geslot, Patric Blaise, Assaf
Kolin, Hannaia Attedgui, Erez Gilad
Zsolt Elter, Philippe Filliatre, Gregoire de
Izarra, Christian Jammes, Imre Pazsit
Chanatip Tippayakul, Saensuk Wetchagarun
Nodal Methods for Reactor Analysis II - Camas
Chairs: Kang-Seog KIM, Oak Ridge National Laboratory and Marjan KROMAR, Institut ”Jozef Stefan”
4:00
4:25
4:50
Three-Dimensional Heterogeneous Variational Nodal Method for PWR Pin-by-pin
Calculation and Control Rod Cusping Effect
A Hybrid Constant Spectral Nodal Method
for Multigroup X,Y-Geometry Sn Eigenvalue
Problems
Investigation of Rehomogenization in the
Framework of Nodal Cross Section Corrections
44
Yongping Wang, Hongchun Wu, Yunzhao Li
Davi Jose M. Silva, Hermes Alves Filho, Ricardo C. Barros
Matteo Gamarino, Daniele Tomatis, Aldo
Dall’Osso, Danny Lathouwers, Jan Leen
Kloosterman, T.H.J.J. van der Hagen
WEDNESDAY AFTERNOON
5:15
A Hybrid Nodal P3/SP3 Axial Transport Solver
for the MPACT 2D/1D Scheme
Shane Stimpson, Benjamin S. Collins, Ang
Zhu, Yunlin Xu
Nuclear Data, Evaluations & Libraries V - Columbine
Chairs: Paul ROMANO, Argonne National Laboratory and Go CHIBA, Hokkaido University
4:00
4:25
4:50
5:15
Neutron Thermalization in Liquid FLiBe
Study of Neutron Scattering in Light Water in
Mistral Experiments Carried Out in EOLE Reactor at CEA Cadarache
A New R-Matrix Evaluation for 16O from Thermal to 6 MeV
Impact of Nuclear Data Uncertainties on Criticality Calculations of the Very High Temperature Reactor Critical Assembly Benchmark
Y. Zhu, Ayman I. Hawari
Juan Pablo Scotta, Gilles Noguere, David
Bernard, Cyrille De Saint Jean, Ignacio Marquez Damian
Luiz C. Leal, Evgeny A. Ivanov, Cecil Lubitz,
Royce Sayer
Friederike Bostelmann, Hans R. Hammer,
Gerhard Strydom, Kiril Velkov, Winfried Zwermann
Sensitivity/Uncertainty Analysis VI - Lupine
Chairs: Andrea ALFONSI, Idaho National Laboratory and Kenji YOKOYAMA, Japan Atomic Energy
Agency
4:00
4:25
4:50
5:15
Scalable Algorithms for Uncertainty Quantification of Multi-Physics Light Water Reactor
Problems with Feedback Effects
Uncertainty Quantification for Full-core
Steady-state PWR Core Simulation with
SCALE and PARCS
MCNP6.1 + JANIS Method to Generate P1
Sensitivity Coefficient Data to Identify ICSBEP
Experiments Sensitive To Angular Scattering
Validation of SIMULATE-3k Against SPERTIII RIA Experiments with Quantification of Nuclear Data Uncertainties
45
Bassam A. Khuwaileh, Paul J. Turinsky
Haining Zhou, Matthew A. Jessee, Andrew M.
Ward, Thomas J. Downar
Ian P. Hill, James Dyrda, Nicolas Soppera
Abdelhamid Dokhane, Gerardo M. Grandi,
Olivier Leray, Dimitri Alexandre Rochman,
Hakim Ferroukhi, A. Pautz
THURSDAY MORNING
Advanced and Small Modular Reactor Designs IV - Ram
Chairs: Nicholas TOURAN TerraPower and (TBD)
4:00
A Versatile Coupled Thermal-Fast Irradiation
Test Reactor
4:25
Modeling and Simulation of the Start-Up of a
Thorium-Based Molten Salt Reactor
Thorium RBWR Physics
4:50
5:15
Multi-Physics, Multi-Scale Modeling of the Xe100 Pebble Bed Reactor
Gilles J. Youinou, Sonat Sen, Roald Wigeland,
Massimo Salvatores, Giuseppe Palmiotti,
David J. Hill, Paul Henslee, Hans D. Gougar,
Phillip J. Finck
Benjamin R. Betzler, Jeffrey Powers, Andrew
Worrall
Phillip M. Gorman, Massimiliano Fratoni, Jasmina L. Vujic, Ehud Greenspan
Eben J. Mulder and Zen Wang
Thursday 8:00-10:05 AM
Experiments IV - Sawtooth
Chairs: George IMEL Idaho State University and Luka SNOJ Institut ”Jozef Stefan”
8:00
8:25
8:50
9:15
9:40
Experimental Validation of Control Rod Reactivity Worth and Fission Rate Distributions for
the CROCUS Reactor
Experimental Validation of A Monte Carlo
Based Toolbox for Self-Powered Neutron and
Gamma Detector Simulation in the OSIRIS
MTR
Validation of the Fast and Thermal Neutron
Flux Profiles in the Advanced Test Reactor for
the AGR-3/4 Experiment
Physics Validation Measurements for HighlyReactive Experiment Packages In the INL Advanced Test Reactor
Study of Experimental Core Configuration of
the Modified STACY for Reactivity Worth Measurement of MCCI Products
46
Adolfo Rais, Mathieu Hursin, Gregory Perret,
A. Pautz
Loic Barbot Vladimir Radulovic, Christophe
Destouches, Jean-Francois Villard, Veronique
Dewynter-Marty, Fadhel Malouch, Franck
Lopez
James W. Sterbentz
David W. Nigg, Joseph W. Nielsen
Satoshi Gunji, Kotaro Tonoike, Kazuhiko
Izawa, Hiroki Sono
THURSDAY MORNING
Fast Reactors III - Camas
Chairs: Nicoloas STAUFF, Argonne National Laboratory and Gérald RIMPAULT, Commissariat à
l’Énergie Atomique et aux Énergies Alternatives
8:00
8:25
8:50
9:15
9:40
Validation of the Newly Implemented 3D TDTMOC Solver of APOLLO3 Code on a Whole
3D SFR Heterogeneous Assembly
Recent Progress in the V&V of the New CEA
APOLLO3® Code : Advanced SFR/LWR Assembly Calculations
Experimental Validation of the New Code
Package APOLLO3-SFR Against ZPPR-10a
Experiment for Critical and Voided Configurations
New Reference APOLLO3 Calculation
Scheme for Sodium Cooled Fast Reactors:
from Sub-Assembly to Full-Core Calculations
SIMMER/PARTISN Analyses of EBR-II Shutdown Heat Removal Tests
Pascal Archier, Jean-Marc Palau, JeanFrancois Vidal, Simone Santandrea, Daniele
Sciannandrone
Jean-Marc Palau, Pascal Archier, JeanFrancois Vidal, Benedicte Roque, Vincent
Pascal, Gerald Rimpault, Fabien Auffret, Didier Schneider, Valentin Jouault
Benedicte Roque, Axel Rizzo Pascal Archier
Vincent Pascal
Pascal Archier, Jean-Marc Palau, JeanFrancois Vidal, Vincent Pascal, Gerald Rimpault, Benedicte Roque, Simone Santandrea
Barbara Vezzoni, Marco Marchetti, Lena
Andriolo,
Fabrizio Gabrielli,
Xue-Nong
Chen, Claudia Matzerath Boccaccini, Andrei Rineiski, Werner Maschek, Koji Morita,
Tatsumi Arima
Multi-Physics Reactor Simulations VII - Limelight C
Chairs: Frederick GLEICHER, Idaho National Laboratory and Marjan KROMAR, Institut ”Jozef Stefan”
8:00
VERA Benchmarking Results for Watts Bar
Nuclear Plant Unit 1 Cycles 1-12
8:25
VERA Benchmarking Results for Krško Nuclear Power Plant Cycle 1
8:50
First Steps Towards a Coupled Code System
for Transient Calculations
Coupled CASMO5-VIPRE Analysis of NonUniform Void Distributions in BWR Lattices
9:15
47
Andrew Godfrey, Benjamin S. Collins, KangSeog Kim, Jeffrey Powers, Robert K. Salko,
Shane Stimpson, William Wieselquist, Kevin
T. Clarno, Jess C. Gehin, Scott P. Palmtag,
Robert O. Montgomery, Rose Montgomery,
Daniel R. Jabaay, Brendan M. Kochunas,
Thomas J. Downar, Nathan A. Capps, Jeffrey
R. Secker
Andrew Godfrey, Matthew A. Jessee, Shane
Stimpson, Benjamin S. Collins, Thomas M.
Evans, Marjan Kromar, Fausto Franceschini,
David A. Salazar
Christian Reiter, Harald Breitkreutz, Anton
Röhrmoser, Winfried Petry
Joshua Hykes, Gerardo M. Grandi, Rodolfo M.
Ferrer, Joel D. Rhodes
THURSDAY MORNING
Reactor Analysis Methods VI - Boiler
Chairs: David NIGG, Idaho National Laboratory and Eugene SHWAGERAUS, Cambridge University
8:00
8:25
8:50
9:15
9:40
Development and Optimization of Weight Window technique in RMC code
On the Mechanisms of Large Amplitude Power
Oscillations in BWRs
Reducing 3D MOC Storage Requirements
with Axial On-the-Fly Ray Tracing
Analysis of Pressurized Water Reactor Pin-byPin Homogenization
GENESIS - A Transport Solver in ThreeDimensional Heterogeneous Geometry Based
on the LEAF Method
Xiao Fan, Kan Wang, Guohui Zhang
Carsten Lange, Dieter Hennig
Geoffrey A. Gunow, Samuel C. Shaner, Benoit
Forget, Kord S. Smith
Zhang Bin, Hongchun Wu, Yunzhao Li,
Liangzhi Cao
Akio Yamamoto, Akinori Giho, Yuki Kato, Tomohiro Endo
Monte Carlo Methods - Columbine
Organized by: William MARTIN, University of Michigan and Yousry AZMY, North Carolina State University
Chairs: Qiong ZHANG, Baker Hughes and Hyung Jin SHIM, Seoul National University
8:00
8:25
8:50
9:15
9:40
Continuous Temperature Representation in
Coupled OpenMC/MOOSE Simulations
Extension of Modified Power Method to MultiDimensional Monte Carlo Simulations
The Application of JMCT to HZP of BEAVRS
Neutron Streaming Investigations with Classic
and Hybrid Monte Carlo Variance Reduction
Methods for the AGN-211-P Research Reactor in Basel
Computing Adjoint-Weighted Parameters with
Reactor Monte Carlo Code RMC
Matthew S. Ellis, Derek R. Gaston, Benoit Forget, Kord S. Smith
Peng Zhang, Hyunsuk Lee, Deokjung Lee
Dunfu Shi, Li Gang, Zhang Baoyin, Li Rui, Hu
Zehua, Fu Yuanguang
Efstathios Vlassopoulos, Valentyn Bykov,
Daniel Siefman, Benjamin Volmert, Manuel
Pantelias
Yishu Qiu, Kan Wang, Massimiliano Fratoni
Verification and Validation of Reactor Analysis Methods IV - Ram
Chairs: Benjamin COLLINS, Oak Ridge National Laboratory and Maria PUSA, VTT Technical Research
Centre of Finland
8:00
8:25
Re-Analysis of the RRR/SEG Fast Thermal
Coupled Facility
Analysis of NCA Tungsten Critical Experiment
by New Monte Carlo Code
48
Andrew Hummel
Hanjoo Kim, Kiho Kim, Sooyoung Choi, Hyunsuk Lee, Deokjung Lee
THURSDAY MORNING
8:50
9:15
9:40
OECD-NEA Expert Group on Multi-Physics
Experimental data, Benchmarks and Validation
Analyses of AP1000 First Core with Direct
Whole Core Calculation Codes
Analysis and Interpretation of the KUCA
ADS Benchmarks with Deterministic Analysis
Codes
James Dyrda, Phillip J. Finck, Nigel (Jim) T.
Gulliford, jean-pascal hudelot, Upendra Singh
Rohatgi, Timothy E. Valentine
Hyunsik Hong, Young Suk Ban, Han Gyu Joo,
David A. Salazar, Fausto Franceschini
Willem F. van Rooijen, Go Chiba, Tomohiro
Endo, Cheolho Pyeon
Sensitivity/Uncertainty Analysis VII - Lupine
Chairs: Cristian RABITI, Idaho National Laboratory and Kenji YOKOYAMA, Japan Atomic Energy
Agency
8:00
8:25
8:50
9:15
9:40
Nuclear Data Uncertainty Propagation Analysis for PWR Depletion Calculation
Development of DRAG-MOC: a Tool for the
Study of Uncertainty Analysis Through the Deterministic OpenMOC Transport Code
Criticality Uncertainty Calculations on Manufacturing Random Parameters for the Benchmark Problem
Multistep Input Reduction for High Dimensional Uncertainty Quantification
Verification of the New Implementations in
SHARK-X For Reactivity Coefficients and Relative Reactivity Worth UQ
Thursday 10:30 AM-12:00 PM
Awards and Closing - Limelight A & B
10:30
11:00
11:30
11:40
Awards and Special Recognition
Meeting Summary
Announcements for M&C 2017
Other
49
Liangzhi Cao, Chao Yang, Tiejun Zu,
Hongchun Wu
Augusto Hernandez Solis, Henrik Sjostrand,
Erwin Alhassan, Petter Helgesson
Gill Soo Lee, Taesuk Hwang
Paul W. Talbot, Congjian Wang, Cristian Rabiti
Mathieu Hursin, Dan Siefman, Gregory Perret,
Peter Grimm, Andreas Pautz
Exhibition Hall Map
1 Idaho National Laboratory
3 Studsvik
4 TerraPower
5 Argonne National Laboratory
6 Oak Ridge National Laboratory
7 Westinghouse
8 University of Michigan
9 Varian Medical Systems
10 Institute of Nuclear Energy Safety Technology
11Unassigned

PHYSOR 2016

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