International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2013)

Sun Valley, Idaho, USA 5-9 May 2013 Volume 1 of 4

ISBN: 978-1-62748-643-9

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Table of Contents Monday, May 6, 2013, 1:30 PM–5:00 PM

Deterministic Transport: Code Development Projects (7288) MICADO: Parallel Implementation of a 2D-1D Iterative Algorithm for the 3D Neutron Transport Problem in Prismatic Geometries

1

François Févotte, Bruno Lathuilière (7344) Benchmarking of Calculation Schemes in APOLLO2 and COBAYA3 for VVER Lattices

13

Nonka Zheleva, Plamen Ivanov, Galina Todorova, Nikola Kolev, Jose J. Herrero (7846) Development of a New Lattice Physics Code ROBIN for PWR Application

27

Shaohong Zhang, Guohua Chen (7855) Overview of Development and Design of MPACT: Michigan Parallel Characteristics Transport Code

42

Brendan Kochunas, Benjamin Collins, Dan Jabaay, Thomas J. Downar, William R. Martin (7856) Parallel 3-D Method of Characteristics in MPACT

54

Brendan Kochunas, Thomas J. Downar, Zhouyu Liu (8071) Assessment of the 2D MOC Solver In MPACT: Michigan Parallel Characteristics Transport Code

66

Benjamin Collins, Brendan Kochunas, Thomas Downar (7242) The A N Neutron Transport by Nodal Diffusion

77

Andrea Barbarino, Daniele Tomatis

Monte Carlo Transport: Code Development Projects (7191) RMC—A Monte Carlo Code for Reactor Physics Analysis

89

Kan Wang, Zeguang Li, Ding She, Jingang Liang, Qi Xu, Yishu Qiu, Jiankai Yu, Jialong Sun, Xiao Fan, Ganglin Yu (7233) Progress and Status of the OpenMC Monte Carlo Code

105

Paul K. Romano, Bryan R. Herman, Nicholas E. Horelik, Benoit Forget, Kord Smith, Andrew R. Siegel (7250) Development of a Dynamic Simulation Mode in Serpent 2 Monte Carlo Code

117

Jaakko Leppänen (7771) Recent Advances in the Mercury Monte Carlo Particle Transport Code

128

Patrick S. Brantley, Shawn A. Dawson, Michael Scott McKinley, Matthew J. O'Brien, David E. Stevens, Bret R. Beck, Eric D. Jurgenson, Chris A. Ebbers, James M. Hall

(7358) Probability of Initiation and Extinction in the Mercury Monte Carlo Code

140

M. S. McKinley, Patrick S. Brantley

Deterministic Transport: Resonance Treatments (7220) Resonance Self-Shielding Effects on Eigenvalue Sensitivity

148

M. Dion, G. Marleau (7467) Modeling Resonance Interference by 0-D Slowing-Down Solution with Embedded Self-Shielding Method

160

Yuxuan Liu, William Martin, Kang-Seog Kim, Mark Williams (7708) On the Overestimation of

238 U

Resonance Capture by Equivalence Theory

175

Qian Zhang, Hongchun Wu, Liangzhi Cao, Youqi Zheng (8049) An Improved Resonance Self-Shielding Method for Heterogeneous Fast Reactor Assembly and Core Calculations

187

Changho Lee, Won Sik Yang (7157) Self-Shielding Models of MICROX-2 Code

196

Jia (Jason)Hou, Kostadin Ivanov, Hangbok Choi (8230) Numerical Computation of Doppler-Broadening in the Resonance Domain

207

Richard Sanchez, Claire Hewko, Simone Santandrea

Monte Carlo Transport: Variance Reduction (7463) A Modified Monte Carlo Local Importance Function Transform Method

219

Kendra P. Keady, Edward W. Larsen (7039) Comparison of Hybrid Methods for Global Variance Reduction in Shielding Calculations

231

Douglas E. Peplow (7274) Fringe Biasing: A Variance Reduction Technique for Optically Thick Meshes

243

Richard P. Smedley-Stevenson (7295) Implementation of Hybrid Variance Reduction Methods in aMultigroup Monte Carlo Code for Deep Shielding Problems

254

Elanchezhian Somasundaram, Todd S. Palmer (7311) Improving Computational Efficiency of Monte Carlo Simulations with Variance Reduction

268

A. Turner, A. Davis

Nuclear Asset Management: Special Session (7758) A General Stochastic Approach to Unavailability Analysis of Standby Safety Systems

280

Hans van der Weide, Mahesh Pandey (7831) Application of Stochastic Optimization to Nuclear Power Plant Asset Management Decisions

292

David P. Morton, Ali Koç, Stephen M. Hess (7206) On the Use of Genetic Algorithm to Optimize Industrial Assets Lifecycle Management Under Safety and Budget Constraints

304

Jeróme Lonchampt, Karine Fessart (7995) Mathematical Framework for the Analysis of Dynamic Stochastic Systems with the RAVEN Code

320

C. Rabiti, D. Mandelli, A. Alfonsi, J. Cogliati, R. Kinoshita

Nuclear Fuels Design, Performance, and Disposition (7208) Evaluation of Effective-Stress-Function Algorithm for Nuclear Fuel Simulation

333

Hyo-Chan Kim, Yong-Sik Yang, Yang-Hyun Koo (7219) DFT Modeling of Adsorption onto Uranium Metal Using Large-Scale Parallel Computing

345

Neal Davis, Rizwan-uddin (7268) First and Second Order Approximations to Stage Numbers in Multicomponent Enrichment Cascades

356

Anthony Scopatz (7329) Mixed-Oxide Fuel Decay Heat Analysis for BWR LOCA Safety Evaluation

366

Ren-Tai Chiang (7385) A Monodimensional Nuclear Fuel Performance Analysis Code, PUMA, Development from a Coupled Approach

375

Jin Sik Cheon, Byoung Oon Lee, Chan Bock Lee, A. M. Yacout (7915) Algorithms for Thermal and Mechanical Contact in Nuclear Fuel Performance Analysis

384

J. D. Hales, D. Andrs, D. R. Gaston (8039) Comparison Between Phase Field Simulations and Experimental Data from Intragranular Bubble Growth in UO2

394

Michael R. Tonks, S. Bulent Biner, Paul C. Millett, David A. Andersson

Monday, May 6, 2013, 6:00 PM–8:00 PM

Poster Session/Reception (7173) Secondary Fusion Coupled Deuteron/Triton Transport Simulation and Thermal-toFusion Neutron Convertor Measurement Guan-bo Wang, Kan Wang, Han-gang Liu, Run-dong Li

404

(7203) Research on Acceleration Method of Reactor Physics Based on FPGA Platforms

413

Chenglong Li, Yu Ganglin, Kan Wang (7204) Parallel Algorithms for 2-D Cylindrical Transport Equations of Eigenvalue Problem

420

Junxia Wei, Shulin Yang (7209) Simulation of the Full-Core Pin-Model by the JMCT Monte Carlo Neutron-Photon Transport Code

427

Li Deng, Gang Li, Baoyin  Zhang, Shu Li, Danhua Shangguan, Yan  Ma, Zehua Hu (7211) Combinatorial Geometry Domain Decomposition Strategies for Monte Carlo Simulations

434

Gang  Li, Baoyin Zhang,  Li Deng, Zeyao Mo,  Zhenzhou Liu, Danhua Shangguan, Yan Ma, Shu Li, Zehua Hu (7216) A 2D/1D Coupling Neutron Transport Method Based on the Matrix MOC and NEM Methods

444

Hongbo Zhang, Youqi Zheng, Hongchun Wu, Liangzhi Cao (7217) Development Status of the Lattice Physics Code in the COSINE Project

454

Yixue Chen, Hui Yu, Shuo Li, Zhiyan Liu, Yuhang Yan (7243) SIMULATE-HEX—The Multi-Group Diffusion Equation in Hexagonal-Z Geometry

462

Sten-Örjan Lindahl (7269) Theory of Particle Detection and Multiplicity Counting with Dead Time Effects

475

Lénárd Pál, Imre Pázsit (7281) Monte Carlo Electron-Photon Transport Using GPUs as an Accelerator: Results for a Water-Aluminum-Water Phantom

487

Lin Su, Xining Du, X.George Xu (7297) New Technique to Reformat Multigroup Cross-Sections for Monte-Carlo Calculation

499

I. R. Suslov, I. V. Tormyshev, K. G. Mel'nikov (7307) Mobile Pit Verification System Based on Passive Special Nuclear Material Verification in Weapons Storage Facilities

508

Jessica N. Paul, Michael R. Chin, Glenn E. Sjoden (7308) Accelerator Shield Design of KIPT Neutron Source Facility

524

Zhaopeng Zhong, Yousry Gohar (7324) Uncollided-Flux Preconditioning for the First Order Transport Equation

535

Michael Rigley, Joseph Koebbe, Clif Drumm (7345) Variance Estimates for Transport in Stochastic Media by Means of the Master Equation

547

Shawn D. Pautz, Brian C. Franke, Anil K. Prinja (7361) Global Variance Reduction for Monte Carlo Reactor Physics Calculations

557

Qiong Zhang, Hany S. Abdel-Khalik (7413) Fast Mix Table Construction for Material Discretization Seth R. Johnson

571

(7469) Resonance Self-Shielding Methodology in MPACT

580

Yuxuan Liu, Benjamin Collins, Brendan Kochunas, William Martin, Kang-Seog Kim, Mark Williams (7607) Discrete Ordinate Quadrature Selection for Reactor-Based Eigenvalue Problems

593

Joshua J. Jarrell, Thomas M. Evans, Gregory G. Davidson (7649) An Implementation Analysis of the Linear Discontinuous Finite Element Method

607

T. L. Becker (7656) A Generalized Framework for In-Line Energy Deposition During Steady-State Monte Carlo Radiation Transport

623

David P. Griesheimer, Mark H. Stedry (7759) Point Kinetics Calculations with Fully Coupled Thermal Fluids Reactivity Feedback

638

Hongbin Zhang, Ling Zou, David Andrs, Haihua Zhao, Richard Martineau (7774) Scalable Load Balancing for Massively Parallel Distributed Monte Carlo Particle Transport

647

Matthew J. O'Brien, Patrick S. Brantley, Kenneth I. Joy (7782) Testing of ENDF71x: A New ACE-Formatted Neutron Data Library Based on ENDF/B-VII.1

659

Steven J. Gardiner, Jeremy L. Conlin, Brian C. Kiedrowski, M. Beth Lee, D. Kent Parsons, Morgan C. White (7788) Reducing Uncertainty in Personnel Dosimetry Calculations in the VHTR Plant Using MAVRIC

671

Timothy Flaspoehler, Bojan Petrovic (7814) A Physics Study for Negative Void Reactivity in Compact Supercritical CO 2 -Cooled

683

Fast Reactor Yonghee Kim, Donny Hartanto, Jeong Ik Lee (7826) Comparison of Serpent and HELIOS-2 as applied for the PWR Few-Group Cross Section Generation

693

Emil Fridman, Jaakko Leppänen, Charles Wemple (7836) Comparison of MCNP6 and Experimental Results for Neutron Counts, Rossi-α, and Feynman-α Distributions

704

A. Talamo, Y. Gohar, S. Sadovich, H. Kiyavitskaya, V. Bournos, Y. Fokov, C. Routkovskaya (7840) Exploration of High-Dimensional Scalar Function for Nuclear Reactor Safety Analysis and Visualization

712

Dan Maljovec, Bei Wang, Valerio Pascucci, Peer-Timo Bremer, Michael Pernice, Diego Mandelli, Robert Nourgaliev (7842) Feasibility of a Monte Carlo-Deterministic Hybrid Method for Fast Reactor Analysis

724

Woong Heo, Woosong Kim, Yonghee Kim, Sunghwan Yun (7897) Computational Characterization and Experimental Validation of the Thermal Neutron Source for Neutron Capture Therapy Research at the University of Missouri

736

John D. Brockman, David W. Nigg, M. Frederick Hawthorne (7988) Development of a New Flux Map Processing Code for Moveable Detector System in PWR Wenhuai Li, Haoliang Lu, Jinggang Li, Zhen Dang, Xiangju Zhang, Yuanbao Wu, Xu Fan

754

(8016) Development and Application of a Hybrid Transport Methodology for Active Interrogation Systems

761

Katherine Royston, William Walters, Alireza Haghighat, Ce Yi, Glenn Sjoden (8024) Assessment and Improvement of the 2D/1D Method Stability in DeCART

776

Shane Stimpson, Mitchell Young, Benajmin Collins, Blake Kelley, Thomas Downar (8043) Advanced Quadratures and Periodic Boundary Conditions in Parallel 3D S n

788

Transport K. Manalo, C. Yi, M. Huang, G. Sjoden (8226) A New Approach for Modeling and Analysis of Molten Salt Reactors Using SCALE

803

J. J. Powers, T. J. Harrison, J. C. Gehin

Tuesday, May 7, 2013, 8:30 AM–12:00 PM

Deterministic Transport: General Methods—I (7302) Novel Fine Flux Integration Methods for the DIABOLO Simplified Transport Solver in COCAGNE

816

David Couyras, François Févotte, Laurent Plagne (7188) Exact-to-Precision Generalized Perturbation for Neutron Transport Calculation

828

Congjian Wang, Hany S. Abdel-Khalik (7271) Homogenization Method Based on the Inverse Problem

842

Ádám Tóta, Mihály Makai (7278) An Angularly Refineable Phase Space Finite Element Method with Approximate Sweeping Procedure

854

József Kópházi, Danny Lathouwers (7343) Computing the Moments of the Neutron Population Using Deterministic Neutron Transport

866

Erin D. Fichtl, Randal S. Baker (7354) Phase-Space Finite Elements in a Least-Squares Solution of the Transport Equation

877

Clif Drumm, Wesley Fan, Shawn Pautz (7359) Neutron Transport in Eulerian Coordinates with Bulk Material Motion

893

Randal S. Baker, Jon A. Dahl, Erin D. Fichtl, Jim E. Morel

Monte Carlo Transport: General Methods—I (7603) Monte Carlo Solution for Uncertainty Propagation in Particle Transport with a Stochastic Galerkin Method Brian C. Franke, Anil K. Prinja

905

(7138) Improved Methods of Handling Massive Tallies in the Reactor Monte Carlo Code RMC

918

Ding She, Kan Wang, Jialong Sun, Yishu Qiu (7190) Internal Neutronics-Temperature Coupling in Serpent 2—Reactivity Differences Resulting from Choice of Material Property Correlations

926

Ville Valtavirta (7214) Improved Mesh Based Photon Sampling Techniques for Neutron Activation Analysis

938

Eric Relson, Paul P. H. Wilson, Elliott D. Biondo (7294) Optimizing the Implementation of the Target Motion Sampling Temperature Treatment Technique—How Fast Can It Get?

950

Tuomas Viitanen, Jaakko Leppänen (7313) Monte Carlo Burnup Code Acceleration with the Correlated Sampling Method— Preliminary Test on a UOX Cell with TRIPOLI-4®

962

Cyril Dieudonne, Eric Dumonteil, Fausto Malvagi, CheikhM’Backè Diop (7314) Accuracy Considerations for Chebyshev Rational Approximation Method (CRAM) in Burnup Calculations

973

Maria Pusa

Nuclear Reactor Core Performance and Optimization—I (7261) Flux Harmonics in Large SFR Cores in Relation with Core Characteristics such as Power Peaks

985

G. Rimpault, L. Buiron, B. Fontaine, P. Sciora, J. Tommasi (7299) Optimization Strategies for Sustainable Fuel Cycle of the BR2 Reactor

996

Silva Kalcheva, G. Van den Branden, Edgar Koonen (7300) Application of the OPTEX Method for Computing Reflector Parameters

1008

A. Hébert, H. Leroyer (7304) Analysis of the Nuclear Measurement Program for an Optimized BR2 Core Configuration

1023

G. van den Branden, Silva Kalcheva, Emre Sikik, Edgar Koonen (7318) Optimization of Multi-Group Cross Sections for Fast Reactor Analysis

1035

M. R. Chin, K. L. Manalo, C. A. Edgar, J. N. Paul, M. P. Molinar, E. M. Redd, C. Yi, G. E. Sjoden (8057) Depletion GPT-Free Sensitivity Analysis for Reactor Eigenvalue Problems

1050

Christopher Kennedy, Hany Abdel-Khalik

Validation, Verification, and Uncertainty Quantification—I (7171) Reactor Physics Verification of the MCNP6 Unstructured Mesh Capability

1064

Timothy P. Burke, Brian C. Kiedrowski, Roger L. Martz, William R. Martin (7172) Uncertainty Quantification of a Radionuclide Release Model Using an Adaptive

1073

Spectral Technique L. Gilli, C. Hoogwerf, D. Lathouwers, J. L. Kloosterman (7198) Adaptive Polynomial Chaos Techniques for Uncertainty Quantification of a Gas Cooled Fast Reactor Transient

1084

Zoltán Perkó, Luca Gilli, Danny Lathouwers, Jan Leen Kloosterman (7259) Application of Adaptive Hierarchical Sparse Grid Collocation to the Uncertainty Qualification of Nuclear Reactor Simulators

1096

Artem Yankov, Thomas Downar (7832) Uncertainty Analysis of Densites and Isotopics: Handling Correlations

1108

Jeffrey A. Favorite, Jerawan C. Armstrong, Tom Burr (7833) Bayesian Calibration of Reactor Neutron Flux Spectrum Using Activation Detectors Measurements: Application to CALIBAN Reactor

1123

J. Cartier, P. Casoli, F. Chappert (7493) Verification of the Three-Dimensional Tetrahedral Grid S N Code THOR

1135

Sebastian Schunert, Rodolfo Ferrer, Yousry Azmy

Nuclear Criticality, Nuclear Data, and Medical Physics (7845) The "Virtual Density" Principle of Neutronics: Toward Rapid Computation of Reactivity Effects in Practical Core Distortion Scenarios

1151

Mark Reed, Kord Smith, Benoit Forget (8061) Fission Matrix-Based Monte Carlo Criticality Analysis of Fuel Storage Pools

1165

Martin Farlotti, Edward W. Larsen (7221) Study on Generating of Thermal Neutron Scattering Cross Sections for LiH

1177

Lipeng Wang, Xinbiao Jiang, Zhumin Zhao, Lixin Chen (7238) Nuclear Data Processing for Energy Release and Deposition Calculations in the MC21 Monte Carlo Code

1188

Timothy H. Trumbull (7326) Development of GPU-Based Monte Carlo Code for Fast CT Imaging Dose Calculation on CUDA Fermi Architecture

1199

Tianyu Liu, Xining Du, Wei Ji, Xie George Xu (7370) Feasibility Study of Noise Analysis Methods on Virtual Thermal Reactor Subcriticality Monitoring

1211

Chidong Kong, Deokjung Lee, Eunki Lee

Multiphysics Power Reactor Simulations—I (7817) Core Follow Calculations with the nTRACER Numerical Reactor and Verification Using Power Reactor Measured Data

1222

Yeon Sang Jung, Han Gyu Joo, JooIl Yoon (7992) Coupling the Core Analysis Program DeCART to the Fuel Performance Application

1234

BISON Frederick N. Gleicher, Benjamin Spencer, Stephen Novascone, Richard Williamson, Richard C. Martineau, Michael Rose, Thomas J. Downar, Benjamin Collins (8036) RAVEN as a Tool for Dynamic Probabilistic Risk Assessment: Software Overview

1247

A. Alfonsi, C. Rabiti, D. Mandelli, J. J. Cogliati, R. A. Kinoshita (8044) The Data Transfer Kit: A Geometric Rendezvous-Based Tool for Multiphysics Data Transfer

1262

S. R. Slattery, P. P. H. Wilson, R. P. Pawlowski (8048) An Evaluation of the Nuclear Fuel Performance Code BISON

1273

D. M. Perez, R. L. Williamson, S. R. Novascone, T. K. Larson, J. D. Hales, B. W. Spencer, G. Pastore (8064) Results from Tight and Loose Coupled Multiphysics in Nuclear Fuels Performance Simulations Using BISON

1285

S. R. Novascone, B. W. Spencer, D. Andrs, R. L. Williamson, J. D. Hales, D. M. Perez

Tuesday, May 7, 2013, 1:30 PM–5:00 PM

Deterministic Transport: General Methods—II (7366) An Advanced Algorithm for Construction of Integral Transport Matrix Method Operators Using Accumulation of Single Cell Coupling Factors

1297

Brian P. Powell, Yousry Y. Azmy (7847) Preserving Spherical Symmetry in Axisymmetric Coordinates for Diffusion Problems

1310

Thomas A. Brunner, Tzanio V. Kolev, Teresa S. Bailey, Andrew T. Till (7952) A New Least-Squares Transport Equation Compatible with Voids

1324

Jon B. Hansen, Jim E. Morel (8030) The Lattice Boltzmann Method Applied to Neutron Transport

1335

Bernard Erasmus, Francois A. van Heerden (8058) 2D/1D Approximations to the 3D Neutron Transport Equation. I: Theory

1346

Blake W. Kelley, Edward W. Larsen (8060) 2D/1D Approximations to the 3D Neutron Transport Equation. II: Numerical Results

1358

Blake W. Kelley, Benjamin Collins, Edward W. Larsen (8062) Thick Diffusion Limit Boundary Layer Test Problems

1369

Teresa S. Bailey, James S. Warsa, Jae H. Chang, Marvin L. Adams

Monte Carlo Transport: General Methods—II (7319) Monte Carlo Mesh Tallies Based on a Kernel Density Estimator Approach Using

1387

Integrated Particle Tracks Kerry L. Dunn, Paul P. H. Wilson (7367) Solution of Stochastic Media Transport Problems Using a Numerical QuadratureBased Method

1399

Shawn D. Pautz, Brian C. Franke, Anil K. Prinja, Aaron J. Olson (7739) Automatic Mesh Adaptivity for CADIS and FW-CADIS Neutronics Modeling of Difficult Shielding Problems

1411

Ahmad M. Ibrahim, Douglas E. Peplow, Scott W. Mosher, John C. Wagner, Thomas M. Evans, Paul P. Wilson, Mohamed E. Sawan (7867) Movable Geometry and Eigenvalue Search Capability in the MC21 Monte Carlo Code

1429

Daniel F. Gill, Brian R. Nease, David P. Griesheimer (7880) Exponentially-Convergent Monte Carlo for the 1-D Transport Equation

1441

Jacob R. Peterson, Jim E. Morel, Jean C. Ragusa (7903) Implementation of On-the-Fly Doppler Broadening in MCNP

1452

William R. Martin, Scott Wilderman, Forrest B. Brown, Gokhan Yesilyurt (7930) On-the-Fly Generation of Differential Resonance Scattering Probability Distribution Functions for Monte Carlo Codes

1466

Eva E. Sunny, William R. Martin

Nuclear Reactor Core Performance and Optimization—II (7272) Criticality and Axial Offset Searches Based on the Integrated Neutron Balance Approach

1482

Aldo Dall'Osso, René van Geemert (7287) Presentation of the MERC Work-Flow for the Computation of a 2D Radial Reflector in a PWR

1500

Thomas Clerc, Alain Hébert, Hadrien Leroyer, Jean-Philippe Argaud, Angélique Ponçot, Bertrand Bouriquet (7350) Evaluation of the Use of Color-Set Geometry During Lattice Physics Constants Generation for Boiling Water Reactor Simulation

1512

Steve Evans, Kostadin Ivanov (7838) A Neutronic Feasibility Study of the AP1000 Design Loaded with Fully Ceramic Micro-Encapsulated Fuel

1522

Chao Liang, Wei Ji (8015) Critical Node Treatment in the Analytic Function Expansion Method for Pin Power Reconstruction

1534

Zhenjia Gao, Yunlin Xu, Thomas Downar (8042) Solving the Bateman Equations in CASMO5 Using Implicit ODE Numerical Methods for Stiff Systems

1551

Joshua M. Hykes, Rodolfo M. Ferrer (7296) Comparison of SERPENT and CASMO-5M for Pressurized Water Reactors Models M. Hursin, A. Vasiliev, H. Ferroukhi, A. Pautz

1565

Validation, Verification, and Uncertainty Quantification—II (8054) A Fission Matrix Based Validation Protocol for Computed Power Distributions in the Advanced Test Reactor

1577

Joseph W. Nielsen, David W. Nigg, Anthony W. LaPorta (7738) Calibration of a Fuel Relocation Model in BISON

1594

Laura P Swiler, Richard L. Williamson, Danielle M. Perez (7176) Validation of the New Code Package APOLLO2.8 for Accurate PWR Neutronics Calculations

1606

A. Santamarina, D. Bernard, P. Blaise, P. Leconte, J-M. Palau, B. Roque, C. Vaglio, J-F. Vidal (7224) Yankee Rowe Isotopics Benchmark Using MCNP-XT

1619

Zhiwen Xu, Chuck Whitmer (7255) A Global Approach of the Representativity Concept Application on a HighConversion Light Water Reactor MOX Lattice Case

1629

Nicolas Dos Santos, Patrick Blaise, Alain Santamarina (7704) Quantitative Uncertainty and Sensitivity Analysis of a PWR Control Rod Ejection Accident

1641

Ihor Pasichnyk, Yann Périn, Kiril Velkov (7306) Method of Characteristics–Based Sensitivity Calculations for International PWR Benchmark

1655

I. R. Suslov, I. V. Tormyshev, O. G. Komlev

Accelerators and Advanced Reactor Concepts (7196) LWR Fuel Assembly Designs for the Transmutation of LWR Spent Fuel TRU with FCM and UO2 -ThO 2 Fuels

1664

Gonghoon Bae, Ser Gi Hong (7244) Random Effects of Fissile Lumps in Molten Salt Reactors

1674

S. Dulla, P. Ravetto, A. K. Prinja (7337) Comparison of Neutron Diffusion and Monte Carlo Models for a Fission Wave

1688

Andrew G. Osborne, Mark R. Deinert (7351) Contact Detection Acceleration in Pebble Flow Simulation for Pebble Bed Reactor Systems

1699

Yanheng Li, Wei Ji (7226) Numerical Studies of the Flux-to-Current Ratio Method in the KIPT Neutron Source Facility

1709

Yan Cao, Yousry Gohar, Zhaopeng Zhong (7712) Spatial and Spectral Effects in Subcritical System Pulsed Experiments S. Dulla, M. Nervo, P. Ravetto, M. Carta

1721

(7966) Estimating Anisotropic Diffusion of Neutrons Near the Boundary of a Pebble Bed Random System

1736

Richard Vasques

Multiphysics Power Reactor Simulations—II (7315) Application of Power Time-Projection on the Operator-Splitting Coupling Scheme of the TRACE/S3K Coupled Code

1748

Damar Wicaksono, Omar Zerkak, Konstantin Nikitin, Hakim Ferroukhi, Rakesh Chawla (7273) Recent Developments in DYNSUB: New Models, Code Optimization and Parallelization

1761

Miriam Daeubler, Nico Trost, Javier Jimenez, Victor Sanchez (7309) On BWR Regional Oscillations with Rotational Symmetry Line Using SIMULATE3K

1773

A. Dokhane, H. Ferroukhi, A. Pautz (7352) Investigations of the Effects of Soluble Boron Tracking on Coupled CTF/NEM, LWR Simulations

1786

M. Biery, M. Avramova, K. Ivanov (7928) Multiphysics Simulations for LWR Analysis

1797

S. Hamilton, K. Clarno, M. Berrill, T. Evans, G. Davidson, R. Lefebvre, R. Sampath, J. Hansel, J. Ragusa, C. Josey (8069) Challenges in the Development of High-Fidelity LWR Core Neutronics Tools

1809

Kord Smith, Benoit Forget

Wednesday, May 8, 2013, 8:30 AM–12:00 PM

Deterministic Transport: MOC Methods (7155) Higher Order Treatment on Temporal Derivative of Angular Flux for TimeDependent MOC

1826

Kosuke Tsujita, Tomohiro Endo, Akio Yamamoto, Yohei Kamiyama, Kazuki Kirimura (7175) Application of the Multigrid Amplitude Function Method for Time-Dependent Transport Equation Using MOC

1839

Kosuke Tsujita, Tomohiro Endo, Akio Yamamoto (7189) Reduction of Discretization Error for Ray Tracing of MOC Through a Correction on Collision Probabilities

1853

Masato Tabuchi, Masahiro Tatsumi, Akio Yamamoto, Tomohiro Endo (7316) High Order Spatial Expansion for the Method of Characteristics Applied to 3-D Geometries Laurent Naymeh, Emiliano Masiello, Richard Sanchez

1865

(7341) The Development and Testing of the HELIOS-2 Lattice Code for Use in Online Cross Section Generation

1877

Z. Karriem, K. Ivanov, C. Rabiti, H. Gougar (7734) A Variable-Order Time-Dependent Neutron Transport Method for Nuclear Reactor Kinetics Using Analytically-Integrated Space-Time Characteristics

1889

Adam J. Hoffman, John C. Lee (7922) The Method of Modular Characteristic Direction Probabilities In MPACT

1901

Zhouyu Liu, Brendan Kochunas, Benjamin Collins, Thomas Downar, Hongchun Wu

Monte Carlo Transport: Hybrid Methods (7258) Improved Convergence of Monte Carlo Generated Multi-Group Scattering Moments

1913

A. G Nelson, W. R Martin (7360) Extending the Subspace Hybrid Method for Eigenvalue Problems in Reactor Physics Calculation

1925

Qiong Zhang, Hany S. Abdel-Khalik (7433) A Hybrid Approach to the Neutron Transport k-Eigenvalue Problem Using NDABased Algorithms

1934

Jeffrey A. Willert, C. T. Kelley, D. A. Knoll, H. Park (7542) Refinement of Overlapping Local/Global Iteration Method Based on Monte Carlo/p-CMFD Calculations

1942

YuGwon Jo, Sunghwan Yun, Nam Zin Cho (7777) A Monte Carlo Implementation of the Predictor-Corrector Quasi-Static Method

1953

Michael W. Hackemack, Jean C. Ragusa, David P. Griesheimer, Justin M. Pounders (8051) Hybrid Method of Deterministic and Probabilistic Approaches for Continuous Energy Neutron Transport Problem

1965

Hyunsuk Lee, Deokjung Lee (8005) A New Implicit Correlation Method for Cross-Correlation Sampling in MCNPXPoliMi

1979

Matthew J. Marcath, Edward W. Larsen, Shaun D. Clarke, Sara A. Pozzi

Multiphysics Power Reactor Simulations—III (8266) Massive Hybrid Parallelism for Fully Implicit Multiphysics

1990

Derek R. Gaston, Cody J. Permann, David Andrs, John W. Peterson (7251) Investigation of the Possibility to Use a Fine-Mesh Solver for Resolving Coupled Neutronics and Thermal-Hydraulics

2002

Klas Jareteg, Paolo Vinai, Christophe Demazière (7264) Natural Equilibria in Steady-State Neutron Diffusion with Temperature Feedback Justin M. Pounders, Ross Ingram

2014

(7320) Hybrid Reduced Order Modeling for Assembly Calculations

2028

Youngsuk Bang, Hany S. Abdel-Khalik, Matthew A. Jessee, Ugur Mertyurek (7335) Analysis of Physics-Based Preconditioning for Single-Phase Subchannel Equations

2040

Joshua E. Hansel, Jean C. Ragusa, Srikanth Allu, Mark A. Berrill, Kevin T. Clarno (8022) A Multilevel Method for Coupling the Neutron Kinetics and Heat Transfer Equations

2052

Apil Tamang, Dmitriy Y. Anistratov

Validation, Verification, and Uncertainty Quantification—III (7201) Extended Forward Sensitivity Analysis of One-Dimensional Isothermal Flow

2064

Matthew Johnson, Haihua Zhao (7374) A New Indirect Measure of Diffusion Model Error

2076

Akansha Kumar, Jim E. Morel, Marvin L. Adams (7375) Converged Accelerated Finite Difference Scheme for the Multigroup Neutron Diffusion Equation

2088

Nicholas Terranova, Domiziano Mostacci, Barry D. Ganapol (8000) Continuous- Energy Eigenvalue Sensitivity Coefficient Calculations in TSUNAMI3D

2103

Christopher M. Perfetti, Bradley T. Rearden (8002) Benchmarks for the Point Kinetics Equations

2119

B. Ganapol, P. Picca, A. Previti, D. Mostacci (8063) Physics-Based Dimension Reduction in Uncertainty Quantification for Radiative Transfer

2147

Adam C. Hetzler, Marvin L. Adams, Hayes F. Stripling IV, William D. Hawkins

Multiphase Flow and Thermal Fluids (7336) CFD Analyses of Natural Circulation in the Air-Cooled Reactor Cavity Cooling System

2158

Rui Hu, W. David Pointer (7828) Improvements, Enhancements, and Optimizations of COBRA-TF

2170

Robert K. Salko, Maria N. Avramova, Russell Hooper, Scott Palmtag, Emilian Popov, John Turner (7835) Thermal Hydraulic Method for Whole Core Design Analysis of an HTGR

2182

Alexander J. Huning, Srinivas Garimella (7946) Second-Order Discretization in Space and Time for Radiation Hydrodynamics

2194

Jarrod D. Edwards, Jim E. Morel, Robert B. Lowrie (7841) A Logical Progression of Steps for Implementation and Testing of the 7Equation, Two-Phase Model into a Computational Framework R. A. Berry

2206

(7943) Entropy Viscosity Method Applied to Euler Equations

2217

M. O. Delchini, J. C. Ragusa, R. A. Berry (7464) Statistical Modeling Support for Calibration of a Multiphysics Model of Subcooled Boiling Flows

2229

A. V. Bui, N. T. Dinh, R. R. Nourgaliev, B. J. Williams

Monte Carlo Transport: Sensitivity and Uncertainty (7168) Methodology, Verification, and Performance of the Continuous-Energy Nuclear Data Sensitivity Capability in MCNP6

2245

Brian C. Kiedrowski, Forrest B. Brown (7169) k-Eigenvalue Sensitivities of Secondary Distributions of Continuous-Energy Data

2257

Brian C. Kiedrowski, Forrest B. Brown (7210) Fuel Temperature Reactivity Coefficient Calculation by Monte Carlo Perturbation Techniques

2268

Hyung Jin Shim, Chang Hyo Kim (7333) The Impact of Fuel Particle Size Distribution on Neutron Transport in Stochastic Media

2279

Chao Liang, Andrew T. Pavlou, Wei Ji (7785) Uncertainty Propagation in Full Core Monte Carlo Depletion Simulations Using Serpent

2291

Timothy Wyant, Bojan Petrovic (7235) Efficiency and Accuracy of the Perturbation Response Coefficient Generation Method for Whole Core COMET Calculations in BWR and CANDU Configurations

2303

Dingkang Zhang, Farzad Rahnema

Wednesday, May 8, 2013, 1:30 PM–5:00 PM

Deterministic Transport: Sn Methods (7317) A Posteriori Error Estimators for the Discrete Ordinates Approximation of the One-Speed Neutron Transport Equation

2314

Sean O’Brien, Yousry Y. Azmy (7376) Characterization of High Order Spatial Discretizations and Lumping Techniques for Discontinuous Finite Element S n Transport

2327

Peter G. Maginot, Jean C. Ragusa, Jim E. Morel (7752) Development of the Adaptive Collision Source (ACS) Method for Discrete Ordinates William Walters, Alireza Haghighat

2339

(7798) An Analytical Discrete Ordinates Solution for a Nodal Model of a TwoDimensional Neutron Transport Problem

2350

João Francisco Prolo Filho, Liliane Basso Barichello (7824) The Spectral Green´s Function Nodal Method for Multigroup Slab-Geometry Fixed-Source S n Problems with Anisotropic Scattering

2361

Welton A. Menezes, Hermes Alves Filho, Ricardo C. Barros (7994) S 2 SA Preconditioning for the S n Equations with Strictly Nonnegative Spatial

2373

Discretization Don E. Bruss, Jim E. Morel, Jean C. Ragusa (8055) Development of a S n Transport Code Based on Discontinous Finite Element

2385

Method and Coarse Mesh Finite Difference Formulation Dong Wook Lee, Han Gyu Joo

Monte Carlo Transport: Implicit Methods (7177) A Radiating Shock Evaluated Using Implicit Monte Carlo Diffusion

2398

Mathew Cleveland, Nick Gentile (7178) Numerical Reproducibility for Implicit Monte Carlo Simulations

2407

Mathew Cleveland, Thomas Brunner, Nick Gentile (7280) Generation of Discrete Scattering Cross Sections and Demonstration of Monte Carlo Charged Particle Transport in the Milagro IMC Code Package

2418

Jonathan A. Walsh, Todd S. Palmer, Todd J. Urbatsch (7282) Monte Carlo Solution Methods in a Moment-Based Scale-Bridging Algorithm for Thermal Radiative Transfer Problems: Comparison with Fleck and Cummings

2430

H. Park, J. D. Densmore, A. B. Wollaber, D. A. Knoll, R. M. Rauenzahn (8066) Temperature-Extrapolation Method for Implicit Monte Carlo-Radiation Hydrodynamics Calculations

2442

Ryan G. McClarren, Todd J. Urbatsch (7293) A New, Coupled Transport-Diffusion Method for Radiative Transfer Calculations

2457

Allan B. Wollaber, James S. Warsa

Algorithms for Advanced Architectures (7262) A Massively Parallel Method of Characteristic Neutral Particle Transport Code for GPUs

2469

William R. Boyd, Kord Smith, Benoit Forget (7334) Efficient Checkpointing Schemes for Depletion Perturbation Solutions on Memory-Limited Architectures

2485

Hayes F. Stripling, Marvin L. Adams, W. Daryl Hawkins (7338) Practical Methods to Improve the Development of Computational Software Andrew G. Osborne, David W. Harding, Mark R. Deinert

2501

(7761) Evaluation of Vectorized Monte Carlo Algorithms on GPUs for a Neutron Eigenvalue Problem

2513

Xining Du, Tianyu Liu, Wei Ji, X. George Xu, Forrest B. Brown (8026) A Spectral Analysis of the Domain Decomposed Monte Carlo Method for Linear Systems

2523

S. R. Slattery, P. P. H. Wilson, T. M. Evans (8070) Provably Optimal Parallel Transport Sweeps on Regular Grids

2535

Michael P. Adams, Marvin L. Adams, W. Daryl Hawkins, Timmie Smith, Lawrence Rauchwerger, Nancy M. Amato, Teresa S. Bailey, Robert D. Falgout (8074) Low-Rank Quasi-Newton Updates for Robust Jacobian Lagging in Newton Methods

2554

Jed Brown, Peter Brune

Nuclear Reactor Systems and Safety (7199) Development and Validation of ALEPH2 Monte Carlo Burn-up Code

2566

Gert van den Eynde, Alexey Stankovskiy, Luca Fiorito, Maxence Broustaut (7260) Reactor Transient Analyses with KIN3D/PARTISN

2578

Fabrizio Gabrielli, Andrei Rineiski, Werner Maschek, Marco Marchetti (7355) Performance of Non-Conventional Factorization Approaches for Neutron Kinetics

2590

S. Dulla, M. Nervo (7949) Solving Implicit Multi-Mesh Flow and Conjugate Heat Transfer Problems with RELAP-7

2602

Ling Zou, John Peterson, Haihua Zhao, Hongbin Zhang, David Andrs, Richard Martineau (8591) Development of an Object-Oriented ORIGEN for Advanced Nuclear Fuel Modeling Applications

2613

S. Skutnik, F. Havlůj, D. Lago, I. Gauld (8032) ANOVA-HDMR Structure of the Higher Order Nodal Diffusion Solution

2625

Pavel M. Bokov, Rian H. Prinsloo, Djordje I. Tomašević (8065) A Continuous Hydrogen Desorption Model from Zirconium Hydride and Subsequent Metal in Vacuum

2637

Xunxiang Hu, Kurt A. Terrani, Brian D. Wirth

Deterministic Transport: Acceleration Techniques (7275) Nonlinear Diffusion Acceleration for the Multigroup Transport Equation Discretized with S n and Continuous FEM With RattleS n ake

2649

Yaqi Wang (7768) Application of Convergence Acceleration to the Reactor Kinetic Equations: A Comparative Study Paolo Picca, Roberto Furfaro, Barry D. Ganapol

2666

(7823) Improvements to the Boundary Projection Acceleration Technique Applied to the Discrete-Ordinates Transport Solver in XYZ Geometries

2678

Emiliano Masiello, Tommaso Rossi (7932) Application of Nonlinear Krylov Acceleration to Radiative Transfer Problems

2690

Andrew T. Till, Marvin L. Adams, Jim E. Morel (8267) A Diffusion Synthetic Acceleration Scheme for Rectangular Geometries Based on Bilinear Discontinuous Finite Elements

2702

Bruno Turcksin, Jean C. Ragusa

Thursday, May 9, 2013, 8:30 AM–12:00 PM

Deterministic Transport: Pn/Hybrid Methods (7236) Surface Harmonics Method for Two-Dimensional Time-Dependent Neutron Transport Problems of Square-Lattice Nuclear Reactors

2713

Victor F. Boyarinov, Anton E. Kondrushin, Peter A. Fomichenko (7276) Efficient Solutions to the NDA-NCA Low-Order Eigenvalue Problem

2725

Jeffrey A. Willert, C. T. Kelley (7284) An Improved Filtered Spherical Harmonic Method for Transport Calculations

2736

Cory Ahrens, Simon Merton (7363) Hybrid S n -Diffusion and S n -P 3 Transport Calculations

2748

Sergiy Manolov, Jim E. Morel, Cristian Rabiti (7525) PROTEUS-MOC: A 3-D Deterministic Solver Incorporating the 2D Method of Characteristics

2759

Abel Marin-Lafleche, Micheal A. Smith, Changho Lee (7923) Comparison of Two Galerkin Quadrature Methods

2771

Jim E. Morel, James S. Warsa, Brian C. Franke, Anil K. Prinja

Monte Carlo Transport: Matrix Methods (7151) A Method for Reducing the Largest Relative Errors in Monte Carlo IteratedFission-Source Calculations

2780

Jessica L. Hunter, Thomas M. Sutton (7170) Calculating Infinite-Medium α-Eigenvalue Spectra with a Transition Rate Matrix Method

2792

Benjamin R. Betzler, Brian C. Kiedrowski, Forrest B. Brown, William R. Martin (7305) A Comparison Between the Fission Matrix Method, the Diffusion Model, and the Transport Model Benjamin Dehaye, François-Xavier Hugot, Cheikh M'Backé Diop

2802

(7325) Explicit Estimation of Higher Order Modes in Fission Source Distribution of Monte-Carlo Calculation

2814

Akio Yamamoto, Kotaro Sakata, Tomohiro Endo (7944) Fission Matrix Capability for MCNP, Part I—Theory

2828

F. B. Brown, S. E. Carney, B. C. Kiedrowski, W. R Martin (7945) Fission Matrix Capability for MCNP, Part II—Applications

2840

S. E. Carney, F. B. Brown, B. C. Kiedrowski, W. R. Martin (8006) Normality of Monte Carlo Criticality Eigenfunction Decomposition Coefficients

2852

Bryan E. Toth, William R. Martin, David P. Griesheimer

Deterministic Transport: Applications (7312) Convergence Studies of Deterministic Methods for LWR Explicit Reflector Methodology

2865

S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz (7839) SNM Neutron Detection Using a Time-Gated Synethic Aperture Hybrid Approach

2877

M. Molinar, C. Yi, C. A. Edgar, K. Manalo, M. Chin, G. Sjoden (8014) Application of Subgroup Decomposition in Diffusion Theory to Gas Cooled Thermal Reactor Problem

2890

Saam Yasseri, Farzad Rahnema (7213) Synergism of the Method of Characteristics and CAD Technology for Neutron Transport Calculation

2900

Zhenping Chen, Dianxi Wang, Tao He, Guozhong Wang, Huaqing Zheng, FDS Team (7303) DOMINO: A Fast 3D Cartesian Discrete Ordinates Solver for Reference PWR Simulations and SPN Validation

2912

T. Courau, S. Moustafa, L. Plagne, A. Ponçot

Monte Carlo Transport: Applications (7310) Preparation of Nuclear Libraries with Deterministic and Stochastic Methods for LWR Reflectors

2924

S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz (7321) A Demonstration of a Whole Core Neutron Transport Method in a Gas Cooled Reactor

2935

Kevin John Connolly, Farzad Rahnema (7409) Improved Diffusion Coefficients Generated From Monte Carlo Codes

2947

Bryan R. Herman, Benoit Forget, Kord Smith, Brian N. Aviles (7522) MC21 Analysis of the MIT PWR Benchmark: Hot Zero Power Results

2962

Daniel J. Kelly III, Brian N. Aviles, Bryan R. Herman (7827) Generation of SFR Few-Group Constants Using the Monte Carlo Code Serpent Emil Fridman, Reuven Rachamin, Eugene Shwageraus

2978

(7834) Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS) Nicholas Horelik, Bryan Herman, Benoit Forget, Kord Smith

2986