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APRIL 15-19, 2007 ~ MONTEREY MARRIOTT HOTEL ~ MONTEREY, CALIFORNIA, USA

 

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Conference Program

 

 

 

Select a Session to go to the list of papers

 

 

 

 

Opening Ceremony: Tomas Diaz de la Rubia, Jasmina Vujic, and Harold McFarlane

 

 

 

Plenary Session 1: Global Nuclear Energy Partnership & High Performance Simulation Capabilities

 

The Global Nuclear Energy Partnership
Dennis Spurgeon

 

Europe Back in HPC World
Jean Gonnord

 

Recent Progress of Supercomputing Research in Nuclear Science in Japan
Hideo Kaburaki, Tashiki Tajima

 

 

 

Parallel Oral Session 1A: Computational Reactor Physics and Particle Transport: Monte Carlo I

 

A Novel Source Convergence Acceleration Scheme for Monte Carlo Criticality Calculations, Part I: Theory
David P. Griesheimer, Bryan E. Toth

 

Wielandt Acceleration for MCNP5 Monte Carlo Eigenvalue Calculations
Forrest Brown

 

Reactor Simulation with Coupled Monte Carlo and Computational Fluid Dynamics
Volkan Seker, Justin W. Thomas, Thomas J. Downar

 

Information Criteria and Higher Eigenmode Estimation in Monte Carlo Calculations
Brian R. Nease, Taro Ueki

 

Converting Boundary-Representation Solid Models to Half-Space Representation Models for Monte Carlo Analysis
J.E. Davis, M.J. Eddy, T.M. Sutton, T.J. Altomari

 

 

 

Parallel Oral Session 1B: Computational Medical Applications

 

A New Electron Energy-Loss Straggling Algorithm in MCNP
Lee T. Harding, Anil K. Prinja, H. Grady Hughes

 

Monte Carlo Modeling of the Elekta Precise Linear Accelerator: Validation of Dose Distribution in a Heterogeneous Water Phantom
B. Juste, M.E. Mota, R. Miró, S. Gallardo, G. Verdú

 

The Use of Monte Carlo Simulation in Improving Reconstruction Quality in Single Photon Emission Computed Tomography
Mingshan Sun, Jasmina L. Vujic, Bruce H. Hasegawa

 

A Computational Dosimetric Comparison Between MCNPX and ATTILA of the Mammosite Radiation Therapy System
J.J. Bergman, T.S. Palmer

 

Impact of Importance Quality in Coupled Electron-Photon-Positron Simulation Using Splitting/Rouletting VR Techniques
Benoit Dionne, Alireza Haghighat

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Parallel Oral Session 1C: High Performance Computing

 

Experiences Applying Unicore Grid Middleware for Nuclear Simulation Tools Like the 3D Reactor Core Model QUABOX/CUBBOX
A. Geiger, J. Luther, G. Ohme, S. Langenbuch, K. Velkov

 

Unstructured 3D Core Calculations with the Descartes System: Application to the JHR Research Reactor
Anne-Marie Baudron, Christoph Döderlein, Pierre Guérin, Jean-Jacques Lautard, Frederic Moreau

 

Computational Physics of Photon Science
Mitsuru Yamagiwa, Sergei Bulanov, Timur Esirkepov, James Koga, Tomohito Otobe, Toshiki Tajima

 

A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure
M. Tani, N. Nakajima, A. Nishida, Y. Suzuki, H. Matsubara, F. Araya, N. Kushida, O. Hazama, K. Kawasaki

 

Wave Propagation Algorithms and Adaptive Mesh Refinement for CFD Simulations of Potential Hydrogen Explosions in Nuclear Containment Structures
D. Calhoun, H. Paillere

 

 

 

Parallel Oral Session 2A: Computational Materials Science: Dislocation Modeling

 

The Motion of Dislocations in Irradiated Materials
Ming Wen, Akiyuki Takahashi, Nasr M. Ghoniem

 

Atomic-Scale Modeling of Dislocation Dynamics in Environment of Radiation Defects
Yu. N. Osetsky, R.E. Stoller, David J. Bacon

 

Molecular Dynamics and Quasi-Two Dimensional Dislocation Dynamics Simulations on the Orowan Pinning Mechanism of a Mixed Dislocation in FCC Metals
Mitsuo Itakura, Tomoko Kadoyoshi, Hideo Kaburaki

 

Discrete Dislocation Dynamics Study and Experimental Validation of the Dislocation – Dispersoids Interactions in PM2000
B. Bako, D. Weygand, M. Samaras, J.-C. Chen, M. Pouchon, W. Hoffelner, P. Gumbsch

 

Brownian Motion of Mesoscopic Dislocation Loops
S.L. Dudarev

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Parallel Oral Session 2B: Computational Thermal Hydraulics

 

Large Eddy Simulation of Wire Wrapped Fuel Pins I: Hydrodynamics in a Periodic Array
Paul Fischer, James Lottes, Andrew Siegel, Giuseppe Palmiotti

 

A One and Two Dimensional PCICE Based Multiphysics Algorithm for Use in Reactor Core Calculations
Lander Ibarra, Brian Lockwood, Cassiano R.E. de Oliveira

 

Coupled BWR Calculations with the Numerical Nuclear Reactor Software System
T. Sofu, J.W. Thomas, D.P. Weber, W.D. Pointer, T.J. Downar

 

The Need for All-Speed Flow Models for Density Driven Flows in Reactor Safety Simulation
D.A. Knoll, R.A. Berry, R.C. Martineau, V.A. Mousseau

 

A Demonstration of Conjugate Heat Transfer and Neutron Transport Coupling for an Axisymmetric Gas-Cooled Reactor
Richard Martineau, Glen Hansen, HyeongKae Park, Cassiano de Oliveira

 

 

 

Parallel Oral Session 2C: High Performance Computing

 

PNFE Component of the UNIC Code
M.A. Smith, G. Palmiotti, C. Rabiti, D. Kaushik, A. Siegel, B. Smith, E.E. Lewis

 

Some Experiments Using Preconditioning Techniques and Second-Order Iterative Methods for the Resolution of the 3D Transient Neutron Diffusion Equation
O. Flores, V. Vidal, G. Verdu, R. Miro

 

Study on the Acceleration of the Neutronics Calculation Based on GPGPU
Yasunori Ohoka, Masahiro Tatsumi

 

High Accuracy Large Scale Monte Carlo and Deterministic Transport Calculations for Critical Systems
S. Langenbuch, A. Seubert, W. Zwermann

 

Comparison of Linear and Quadratic Discontinuous Spatial Finite Element Methods for Parallel SN Transport on Triangles
Jae H. Chang, James S. Warsa

 

 

 

Parallel Oral Session 3A: Computational Reactor Physics and Particle Transport: Discrete Ordinates

 

A Quantitative Theory of Angular Truncation Errors in 3-D Discrete Ordinates Calculations
Edward W. Larsen, Allan B. Wollaber

 

Krylov Iterative Methods and Synthetic Acceleration for Transport in Binary Statistical Media
Erin D. Fichtl, James S. Warsa, Anil K. Prinja

 

Coarse Mesh Rebalance Acceleration Revisited: Krylov Preconditioning
Han Jong Yoo, Nam Zin Cho

 

Subcell SN Sweeping for Meshes with Reentrant Cells
Frederick N. Gleicher, James S. Warsa, Jim E. Morel, Anil K. Prinja

 

Solution Algorithms for a PN-1-Equivalent SN Angular Discretization of the Transport Equation in One-Dimensional Spherical Coordinates
James S. Warsa, Jim E. Morel

 

Nonlinear Weighted Flux Methods for Particle Transport Problems in 2D Cartesian Geometry
Loren Roberts, Dmitriy Y. Anistratov

 

 

 

Parallel Oral Session 3B: Computational Thermal Hydraulics

 

Eulerian Two-Phase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis
W. David Pointer, Adrian Tentner, Tanju Sofu, David Weber, Simon Lo, Andrew Splawski

 

Extension of the PCICE-FEM Method to Homogeneous, Equilibrium Two-Phase Flow
Ray A. Berry, Richard C. Martineau

 

Direct Numerical Simulation of Boiling Multiphase Flows: State of the Art Modeling, Algorithmic and Computer Needs
R. Nourgaliev, D. Knoll, V. Mousseau, R. Berry

 

A Parallel Interface Capture Method for Compressible Flows with the TRITON Code
Samuel Kokh

 

Simulation of Chaotic ABC Flow Using Parallel Modified Nodal Integral Method
Suneet Singh, Rizwan Uddin

 

Numerical Simulation of Sidewall Effects on the Acoustic Field of Transonic Cavity Flow
Zhisong Li, Debashis Basu, Awatef Hamed

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Parallel Oral Session 3C: Computational Reactor Physics and Particle Transport: Monte Carlo II

 

Improved Implicit Monte Carlo Schemes Based on the Difference Formulation
Richard P. Smedley-Stevenson

 

A Fokker-Planck Method for Modeling Compton Scattering in Implicit Monte Carlo Simulations
Jeffery D. Densmore, James S. Warsa, Jim E. Morel

 

Transition and Collision Biasing in a Variance Reduction Scheme for Criticality Calculations
Stavros Christoforou, J. Eduard Hoogenboom

 

General Tally Support and Post Processing in a Modern Monte Carlo Transport Code
M. Scott McKinley

 

Particle Population Diagnostics in Iterated-Source Monte Carlo Methods
Taro Ueki

 

The MC21 Monte Carlo Transport Code
T.M. Sutton, T.J. Donovan, T.H. Trumbull, P.S. Dobreff, E. Caro, D.P. Griesheimer, L.J. Tyburski, D.C. Carpenter, H. Joo

 

 

 

Plenary Session 2: Nuclear Energy Across the Globe

 

On the Role of Validated Simulations Within the European Nuclear Fission Technology Platform
Dan Gabriel Cacuci

 

Status of Nuclear Power Program in Far-Eastern Asian Countries
Chang Hyo Kim

 

Advances in Monte Carlo Methods for Global Reactor Analysis
William Martin

 

 

 

Parallel Oral Session 4A: Computational Reactor Physics and Particle Transport: Diffusion Theory

 

Calculation of the Eigenfunctions and Corresponding Eigenvalues of the Two-Group Diffusion Equation in Heterogeneous Systems
C. Demazičre, C. Sunde

 

Performance of the Diffusion and Simplified PN Theories for BWR Pin-by-Pin Fine Mesh Core Analyses
Akio Yamamoto, Kenichi Tada, Yasunori Kitamra, Yoshihiro Yamane, Masato Watanabe, Hiroshi Noda

 

Goal-Oriented hp-Mesh Adaptation for 1-D Multigroup Diffusion Equations
Yaqi Wang, Jean Ragusa

 

Flux-Limited Diffusion Coefficients in Reactor Physics Applications
Justin Pounders, Farzad Rahnema, Ronaldo Szilard

 

3D Whole Core Fine Mesh Multigroup Diffusion Calculations by Domain Decomposition Through Alternate Dissections
José-Javier Herrero, Carol Ahnert, Jose-Maria Aragones

 

 

 

Parallel Oral Session 4B: Nuclear Reactor Analysis

 

Modeling and Simulation Needs for Future Generation Reactors
H.S. Khalil

 

High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON
Mark D. DeHart, Ian C. Gauld, Mark L. Williams

 

New Modelling of LWR Assemblies Using the Apollo2 Code Package
J.F. Vidal, O. Litaize, D. Bernard, A. Santamarina, C. Vaglio-Gaudard, R. Tran

 

The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project
Andreas Pautz, Hans-Wilhelm Bolloni, Karl-Albert Breith, Rene van Geemert, Jochen Heinecke, Greg Hobson, Stephan Merk, Baptiste Pothet, Florin Curca-Tivig

 

Experience in Simulation of Startup Measurements in the VVER-440 Reactor Using the KIKO3D Code
Gy. Hegyi, A. Keresztúri, Cs. Maráczy

 

 

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Parallel Oral Session 4C: Computational Materials Science: Radiation Damage & Fe-Cr Alloys

 

Modeling of Irradiation Damage Effects on the Ductility of Metals
A. Arsenlis, B.D. Wirth, W.G. Wolfer

 

Simulations of Radiation Collision Cascades in Dense Nuclear Materials
K. Nordlund, C. Björkas, N. Juslin, K. Vörtler, L. Malerba, D. Terentyev

 

Bridging Molecular Dynamics and Kinetic Monte Carlo in Modelling Nuclear Materials
Naoki Soneda, Akiyoshi Nomoto, Akiyuki Takahashi

 

Thermodynamic Properties of FeCr Potentials and Simulation of Radiation Damage in FeCr
Carolina Björkas

 

Heterogeneous Precipitation in FeCr Alloys
M. Caro, A. Caro

 

 

 

Parallel Oral Session 5A: Computational Reactor Physics and Particle Transport: Kinetics and Time-Dependence

 

Asymptotic Analysis of Time-Dependent Neutron Transport Coupled with Isotopic Depletion and Radioactive Decay
Patrick S. Brantley

 

A Multi-Scale Approach for the Neutronic Kinetics Equations Using the Mixed Dual Solver MINOS
S. Chauvet, A. Nachaoui, A.M. Baudron, J.J. Lautard

 

Investigation of the Validity of the Point-Kinetic Approximation and of the Break-Frequency Method in 2-D Subcritical Systems
C. Sunde, C. Demaziere, I. Pázsit

 

High Resolution Time Integration for the Spherical Harmonics Equations
Ryan G. McClarren, James Paul Holloway

 

Treatments of Time-Derivatives of Neutron Kinetics Equation for Sub-Critical System with Neutron Source and Monte Carlo Calculation
Hiroshi Sekimoto, Kohei Iwanaga, Takamasa Mori

 

Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems
S. Dulla, P. Ravetto, P. Picca, D. Tomatis, J.R. Maiorino, T. Carluccio, A. Antunes, A. Santos, F. de Oliveira , R.S. Santos

 

 

 

Parallel Oral Session 5B: Nuclear Reactor Analysis

 

UNIC: Ultimate Neutronic Investigation Code
G. Palmiotti, M. Smith, C. Rabiti, M. Leclere, D. Kaushik, A. Siegel, B. Smith, E.E. Lewis

 

Use of the APOLLO2 Code for BWR Assembly Analysis
Laure Mondelain, Igor Zmijarevic, Jean Michel Do, Veronique Bellanger

 

The Doppler Defect Benchmark: Overview and Summary of Results
Russell D. Mosteller

 

Simplification of Multi-Group Cross-Section Processing for Large Depletion Calculations in TRITON
Mark D. DeHart

 

TRITON/NEWT Calculation of the CORAIL Assembly for Plutonium Recycling in PWR
Francesco Ganda, Miodrag Milosevic, Ehud Greenspan, Temitope Taiwo

 

Full MOX ABWR Neutron Characterization with Void Increase: The FUBILA Program
P. Blaise, N. Thiollay, N. Huot, P. Fougeras, V. Laval, A. Roche

 

 

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Parallel Oral Session 5C: High Performance Computing

 

Dynamic Load Balancing of Parallel Monte Carlo Transport Calculations Via Spatial Redecomposition
Matthew J. O'Brien

 

Load Balancing Strategy for Radiation Transport Code EVENT
Aliva Pattnaik, Cassiano R. E. de Oliveira

 

Computer Simulation of Bubble Formation
Z. Insepov, T. Bazhirov, G. Norman, V. Stegailov

 

Domain Decomposition Methods for Core Calculations Using the MINOS Solver
Pierre Guerin, Anne-Marie Baudron, Jean-Jacques Lautard

 

Improved Parallelization of the Modular Ray Tracing in the Method of Characteristics Code DeCart
B. Kochunas, T.J. Downar, Mohamed Sayeed, J.W. Thomas

 

Osiris: A Modern, High-Performance, Coupled, Multi-Physics Code For Nuclear Reactor Core Analysis
Richard Procassini, Kyle Chand, Christopher Clouse, Robert Ferencz, Jeffrey Grandy, William Henshaw, Kevin Kramer, Dennis Parsons

 

 

 

Poster Session I: Computational Materials Science

 

Characteristics of Self-Point Defects and Their Anisotropy Migration in Elastic Stress Fields of Dislocations in FCC Pu
N.A. Dubasova, V.M. Chernov, A.B. Sivak

 

Energetic, Kinetic and Crystallographic Characteristics of Self-Point Defects in Vanadium and Iron Crystals
A.B. Sivak, V.M. Chernov, V.A. Romanov

 

First Principles Calculations on the Grain Boundary Decohesion of Iron and Nickel by Oxygen
Masatake Yamaguchi, Hideo Kaburaki

 

Materials in Extreme Conditions the Critical Phenomena and Phase Transfer in the Dynamic Destruction
A.Ya Uchaev, V.T. Punin, N.I. Selchenkova, E.V. Kosheleva

 

Mechanical Stresses in Fuel Particles and Graphite of High Temperature Reactors
B. Boer, A.M. Ougouag, G.K. Miller, J.L. Kloosterman

 

Molecular Dynamics Simulations of Local Environment Dependence of Self-Interstitial Atom Diffusion in BCC Fe-Cr Alloys
Chao Jiang, S.G. Srivilliputhur, A. Caro, M. Caro, S. Maloy

 

Self-Point Defects Characteristics and Their Dependence on <1120> {0001} Dislocation Stress Field in Alpha-Zr
D.A. Chulkin, V.M. Chernov, A.B. Sivak

 

Stability of Uncommon Interstitials in Fe
D. Terentyev, L. Malerba, P. Klaver, F. Willaime

 

The Universal Properties of Metals Behavior in the Dynamic Destruction Phenomenon in a Wide Range of Longevity Under the Influence of High-Power Pulses of Radiation
V.T. Punin, A.Ya. Uchaev, N.I. Selchenkova, L.A. Platonova, E.V. Kosheleva

 

Heterogeneous Precipitation in Fe-Cu Alloys
P. Erhart, M. Caro, A. Caro

 

Computational Analysis of Neutron-Absorbing Structural-Amorphous Metal (SAM) Coatings for Spent Nuclear Fuel (SNF) Container to Enhance Criticality Safety Controls
Jor-Shan Choi, Chuck Lee, Dan Day, Mark Wall, Cheng Saw, Joe Farmer, Moe Boussoufi, Ben Liu, Hal Egbert

 

 

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Poster Session I: Nuclear Reactor Analysis

 

Computational Benchmark of the Doppler Reactivity Defect
Jeremy L. Conlin

 

ENDF/B-V, ENDF/B-VI, and ENDF/B-VII.0 Results for the Doppler-Defect Benchmark
Russell D. Mosteller

 

DRAGON Evaluation of the Benchmark for the Doppler Reactivity Defect
J. Le Mer, G. Marleau

 

Application of SUHAM-U Code for Calculation of the Computational Benchmarks for the Doppler Reactivity Defect
V.F. Boyarinov, N.V. Sultanov

 

Analysis of Doppler Reactivity Benchmark
Suhail Ahmad Khan, R. Karthikeyan, V. Jagannathan

 

Doppler Coefficient of Reactivity - Benchmark Calculations for Different Enrichments of UO2
L. Thilagam, C. Sunil Sunny, K.V. Subbaiah, K. Devan, Young-Seok Lee, V. Jagannathan

 

KENO Continuous Energy Calculations for a Suite of Computational Benchmarks for the Doppler Reactivity Defect
Mark D. DeHart, Sedat Goluoglu, Michael E. Dunn

 

 

 

Poster Session I: Computational Reactor Physics and Particle Transport

 

Optimal Perturbation Size for Matrix Free Newton/Krylov Methods
Yunlin Xu, Thomas J. Downar

 

Earthquakes and Pebble Bed Reactors: Time-Dependent Densification
Abderrafi M. Ougouag, Joshua J. Cogliati

 

Analysis of the Quasidiffusion Method on Two-Dimensional Problems with Spatially Periodic Media
Adrian Constantinescu, Dmitriy Y. Anistratov

 

Reconstruction of the Local Neutron-Physical Functionals in Surface Harmonics Method
V.F. Boyarinov, V.A. Nevinitsa

 

High Power Gamma Ray Source by Radiation Damping
James Koga, Mitsuru Yamagiwa

 

Automatic Differentiation with Code Coupling and Applications to SCALE Modules
Bradley T. Rearden, James E. Horwedel

 

Using Homogenized Macroscopic Group Cross Sections in Continuous-Energy Monte Carlo Neutron Transport Calculations with MCNP
J.C. Kuijper, S.C. van der Marcj, A. Hogenbirk

 

Feasibility of Using a Universal Point Wise Energy Grid or a Very Fine Multi-Group Energy Grid in MORET5 Criticality Calculations
Joachim Miss, Olivier Jacquet, Benoit Forestier, Wim Haeck, Bernard Verboomen

 

An Easy Way to Carry Out 3D Uncertainty Analyses
Alfred Hogenbirk

 

Analytical Solution of a Simplified Transport Problem with Continuous Energy for Testing Monte Carlo Procedures
J. Eduard Hoogenboom

 

VHTR Numerical Benchmark Based on the Compact Nuclear Power Source Experiments
Hyung-Kook Joo, Temitope A. Taiwo, Won Sik Yang

 

A P1 Benchmark for Time Dependent Thermal Radiative Transfer
Ryan G. McClarren, James Paul Holloway, Thomas A. Brunner

 

 

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Parallel Oral Session 6A: Computational Reactor Physics and Particle Transport: Characteristics, Diffusion, Transport, and Hybrid Methods

 

A Hybrid Monte Carlo-Diffusion Method for Radiation Transport on Adaptive Mesh Refinement-Type Meshes
Jeffery D. Densmore, Thomas M. Evans, Michael W. Buksas

 

A Hybrid Block-Oriented Discrete Ordinates and Characteristics Method Algorithm for Solving Linear Boltzmann Equation
Ce Yi, Alireza Haghighat

 

A New Paradigm for Whole Core Neutron Transport Without Homogenization
E.E. Lewis, M.A. Smith, G. Palmiotti

 

Singular Characteristic Tracking Algorithm for Improved Solution Accuracy of the Discrete Ordinates Method with Isotropic Scattering
Jose I. Duo, Yousry Y. Azmy

 

The Analytical Solution to the Multigroup Diffusion Equation in One-Dimensional Plane, Cylindrical and Spherical Geometries
B.D Ganapol

 

 

 

Parallel Oral Session 6B: Nuclear Reactor Analysis

 

Application of Nodal Equivalence Parameters for Prismatic VHTR Core Analysis
C.H. Lee, Z. Zhong, T.A. Taiwo, W.S. Yang, H.K. Joo

 

Neutronics Assessment of Stringer Fuel Assembly Designs for the Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR)
F.J. Szakaly, T.K. Kim, T.A. Taiwo

 

Monte Carlo Equilibrium Cycle Analysis of a Deep-Burn MHR Core Charged with Kernel-Based TRISO Fuel
Yonghee Kim, Francesco Venneri

 

Determination of the Equilibrium Composition of Cores with Continuous Fuel Feed and Removal Using MOCUP
Massimiliano Fratoni, Ehud Greenspan

 

Sensitivity Analysis of the Kinetic Behaviour of a Gas Cooled Fast Reactor to Variations of the Delayed Neutron Parameters
W.F.G. van Rooijen, D. Lathouwers

 

 

 

Parallel Oral Session 6C: Computational Materials Science

 

Radiation Interaction Analysis for BWR Channel Shadow Corrosion
Ren-Tai Chiang, Aylin Yilmazbayhan

 

Experimental Benchmarking of Pu Electronic Structure
J.G. Tobin

 

A Numerical Investigation of the LLNL/AWE/CEA Fragmentation Experiments on HELEN
C.S. Debonnel, J.L. Vierne, F. Bonneau, P. Combis

 

A Three-Dimensional Meso-Scale Modeling for Helium Bubble Growth in Metals
Tomoaki Suzudo, Hideo Kaburaki, Eiichi Wakai

 

Synthesis and Performance of Fe-Based Amorphous Alloys for Nuclear Repository Applications
Larry Kaufman, J.H. Perepezko, K Hildal

 

 

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Parallel Oral Session 7A: Computational Reactor Physics and Particle Transport: Cross Sections and Uncertainties

 

Generation of Multi-Group Cross Sections and Scattering Matrices with the Monte Carlo Code MCNP5
J. Eduard Hoogenboom, Vladimir A. Khotylev, John M. Tholammakkil

 

Generation of Subgroup Weights Employing Shielded Cross Section Conservation Principle for Representative Pin Cells
Leonid Pogosbekyan, Han Gyu Joo, Chang Hyo Kim, Kang Seog Kim

 

Evaluation of BWR Core Attributes Uncertainties due to Multigroup Cross Section Uncertainties
Matthew A. Jessee, Hany S. Abdel-Khalik, Paul J. Turinsky

 

ENDF/B-VII.0, ENDF/B-VI, JEFF-3.1, and JENDL-3.3 Results for Unreflected Plutonium Solutions and MOX Lattices
Russell D. Mosteller

 

Effects of Uncertainties in Lead Cross Section Data in Monte Carlo Analysis of Lead Cooled and Reflected Reactors
Miodrag Milosevic, Ehud Greenspan, Jasmina Vujic

 

 

 

Parallel Oral Session 7B: Nuclear Reactor Analysis

 

Investigations on the Migration Mode Method (MMM) for Reactor Calculations
Aldo Dall'Osso, Augusto Gandini, Rossella Rotella

 

A PWR Assembly Computational Scheme Based on the DRAGON v4 Lattice Code
R. Le Tellier, A. Hebert

 

The Calculation of Resonance Parameters for the DeCART MOC Code
Yunlin Xu, Zhenjia Gao, Thomas Downar

 

LPPF Prediction in a BWR Fuel Lattice Using Artificial Neural Networks
Jose L. Montes, Juan J. Ortiz, Juan L. François, Cecilia M. Martín-del-Campo

 

BWR Stability and Bifurcation Analysis Using a Novel Reduced Order Model (Impact of Model Modifications)
C. Lange, D. Hennig, V. Garcia i Llorens

 

 

 

Parallel Oral Session 7C: Computational Materials Science

 

Advances in the Density Functional Calculations of Structures and Dynamics of Defects in Nuclear Materials
C. Domain

 

Stability and Mobility of Self-Interstitial Atoms and their Clusters in Fe-Cr Alloys: An Atomic-Level Study
D.A. Terentyev, L. Malerba, P. Klaver, P. Olsson

 

Finite-Temperature Simulation Based on the Lanczos Algorithm for Low-Dimensional Strongly Correlated Electron Systems; High-Temperature Superconducting Cuprates
Toru Sakai

 

Ab Initio Determination of Cr Interactions with Point Defects in BCC Fe
P. Olsson, C. Domain, J. Wallenius

 

Parallel Kinetic Monte Carlo
E. Martinez, J. Marian, M. Kalos

 

 

 

Parallel Oral Session 8A: Computational Reactor Physics and Particle Transport: Nodal and Characteristic Methods

 

Advanced Transverse Integration for the Method of Characteristics
Francois Fevotte, Simone Santandrea, Richard Sanchez

 

A Nodal Expansion Method for Solving the Multigroup SP3-Equations in the Reactor Code DYN3D
C. Beckert, U. Grundmann

 

Axial Dependence of Homogenized Cross Sections Used for Nodal Analysis of the Boiling Water Reactor
B. Kochunas, M. Hursin, T.J. Downar, C. Glass

 

Spectral Green's Function Linear-Nodal Method for Monoenergetic X,Y-Geometry External Source Discrete Ordinates Problems
Dany S. Dominguez, Ricardo C. Barros

 

An Unstructured Characteristics Scheme with a Linear Expansion for Both Fluxes and Cross Sections
Simone Santandrea, Pierre Bellier

 

A Method of Characteristics Solution to the OECD/NEA 3D Neutron Transport Benchmark Problem
J. Bryce Taylor, Dave Knott, Anthony J. Baratta

 

 

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Parallel Oral Session 8B: Nuclear Reactor Analysis

 

Benchmarking WIMS/RFSP Against Measurement Data of Wolsong Nuclear Power Plants
Chang Je Park, Hangbok Choi

 

Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms
C. Martin-del-Campo, R. Carmona, I.P. Oropeza, J.L. François, M.A. Palomera

 

Comparison of Two-Step Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR-400 Problem
Hyun Chul Lee, Kang-Seog Kim, Jae Man Noh

 

Neutronic Analysis on a Low Enriched Uranium Coupled Reactor Consisting of Pulse Cores and a Laser Module
Hiroki Takezawa, Toru Obara

 

Degradation Monitoring in IRIS Steam Generators
Bulent Alpay, James Paul Holloway, John C. Lee

 

Implementation of Component Concept in Silene 2D/3D Pre & Post Processing GUI
Zarko Stankovski

 

 

 

Parallel Oral Session 8C: Nuclear Methods for Nonproliferation

 

Pulse-Shape Discrimination for Identification of Neutron Sources Using the BC-501A Liquid Scintillator
M. Scott Flaska, S.A. Pozzi

 

A Sequential Least Squares Algorithm for Neutron Spectrum Unfolding from Pulse-Height Distributions Measured with Liquid Scintillators
Yunlin Xu, Marek Flaska, Sara Pozzi, Vladimir Protopopescu, Thomas Downar

 

Simulation of Cargo Container Interrogation by D-D Neutrons
Tak Pui Lou, Arlyn Antolak

 

Benchmarking of Monte Carlo Simulations of Thermal Neutron Kinetics and Differential Die-Away Analysis
K.A. Jordan, T. Gozani, J. Vujic

 

Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation
Shaun Clarke, Thomas Downar, Sara Pozzi, Marek Flaska, John Mihalczo, Enrico Padovani, Alan Hunt

 

Monte Carlo Models of Neutron Detection with Organic Scintillators
Sara A. Pozzi, Marek Flaska, Imre Pazsit, Andreas Enqvist

 

 

 

Poster Session II: Computational Medical Applications

 

Evaluation of a Heterogeneous Coarse Mesh Photon Transport Method Using a Simplified Lung Model
Megan Satterfield, Farzad Rahnema, Dingkang Zhang, Tim Fox

 

Fast Dose Planning Monte Carlo Simulations in Inhomogeneous Phantoms Submerged in Uniform, Static Magnetic Fields
Ricardo Yanez, James F. Dempsey

 

Simulation of Electron and Photon Transport Through Tumorous and Surrounding Tissues with 3D Monte Carlo Codes
Y.Z. Kandiev, A.A. Malakhov, S.I. Samarin, E.V. Serova, S.G. Spirina

 

 

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Poster Session II: Computational Reactor Physics and Particle Transport

 

A Data Analysis Code for MCNP Mesh and Standard Tallies
Kenneth A. Van Riper

 

Multi-Group Nondiffusion Neutron-Physical Characteristics of the Nuclear Reactor Cell with Axial Symmetry
Tamara Poveschenko

 

A Novel Source Convergence Acceleration Scheme for Monte Carlo Criticality Calculations, Part II: Implementation and Results
Bryan E. Toth, David P. Griesheimer

 

Convergence Testing for MCNP5 Monte Carlo Eigenvalue Calculations
Forrest Brown, Brian Nease, Jesse Cheatham

 

A Monte Carlo Method for Calculating Initiation Probability
Gregory Greenman, Richard Procassini, Christopher Clouse

 

New Capabilities in Mercury: A Modern Monte Carlo Particle Transport Code
Richard Procassini, Dermott Cullen, Gregory Greenman, Christian Hagmann, Kevin Kramer, Scott McKinley, Matthew O'Brien, Janine Taylor

 

A k-eff Search Capability in MC21
R.E. Morrow, T.H. Trumbull, T.J. Donovan, T.M. Sutton

 

Interpolation Methods and Splice Options for Three-Dimensional Transport Calculations Using PARTISN
Matthew A. Jessee, Carl E. Yehnert

 

Fourier Analysis of Parallel Block-Jacobi Splitting with Transport Synthetic Acceleration in Two-Dimensional Geometry
Massimiliano Rosa, James S. Warsa, Jae H. Chang

 

Treatment of the Central Singularity in the Conformal Mapping Approach to the Analytic Nodal Method in Cylindrical Geometry
Rian H. Prinsloo, Djordje I. Tomasevic

 

Multi-Dimensional Automatic Mesh Refinement for the Multigroup SPN Equations
Yaqi Wang, Jean Ragusa

 

Development and Performance of the Analytic Nodal Diffusion Solver "ANDES" in Multigroups for 3D Rectangular Geometry
Juan-Andres Lozano, José M. Aragonés, Nuria García-Herranz

 

The LTSN Exponential Nodal Method for One-Speed XY-Geometry Discrete Ordinates Problems in Heterogeneous Media
Eliete Biasotto Hauser, Marco Tullio Vilhena, Ricardo C. Barros

 

Comparison of Different Shielding Materials Used at Proton Accelerators and Cost-Benefit Analysis
Vahagn Nazaryan, Cynthia E. Keppel

 

Monte Carlo Particle Transport Capability for Inertial Confinement Fusion Applications
Patrick S. Brantley, Linda M. Stuart

 

Reactor Physics Characterization of Transmutation Targeting Options in a Sodium Fast Reactor
Samuel E. Bays

 

 

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Poster Session II: Numerical Methods and Software Architecture for Multiphysics Simulations

 

The Multi-Physics User-Friendly Gas-Dynamics Code Visual Tsunami 2.0
C.S. Debonnel, L. Trubov, C.A. Zeballos, P.F. Peterson

 

Software Design of SHARP
A. Siegel, T. Tautges, A. Caceres, D. Kaushik, P. Fischer, G. Palmiotti, M. Smith, J. Ragusa

 

PIC-MCC Simulation of the Electrical Breakdown in a Plasma Focus Device
M. Frignani, G. Grasso, F. Rocchi, M. Sumini

 

 

 

Poster Session II: Nuclear Methods for Nonproliferation

 

Analytical and Numerical Modelling of the Detection Statistics of Emission from a Fissile Sample with Absorption
Andreas Enqvist, Imre Pazsit, Sara Pozzi

 

 

 

Poster Session II: Nuclear Reactor Analysis

 

A New Strategy for Optimal Fuel Core Loading Pattern Design in PWR Nuclear Power Reactors
Niloofar Mohseni, Mehrdad Boroushaki, Mohammad B. Ghofrani, Mohammad H. Raji

 

A Populational Particle Collision Algorithm Applied to a Nuclear Reactor Core Design Optimization
Wagner F. Sacco, Hermes Alves Filho, Cassiano R.E. de Oliveira

 

An Algorithm for Efficient Computation of Multi-Layer Neutron Reflection and Transmission Conditions
Marcos P. de Abreu

 

Cross-Section Parameterization Using Quasi-Regression Approach
Pavel M. Bokov, Rian Prinsloo

 

Program CSA-3 of Reloading Pattern Optimization in Three-Dimensional Module
Bingheng Wang, Zhihong Liu, Gong Shi, Yongming Hu

 

Reactivity Oscillations in Molten Salt Reactors
S. Dulla, C. Nicolino, P. Ravetto

 

 

 

Plenary Session 3: National Ignition Facility and Forefront of High-Performance Computing in Nuclear Systems

 

The National Ignition Facility: Fusion Ignition in the Laboratory and New Frontiers in High Energy Density Science
Ed Moses

 

Improving Nuclear Power Economics Via Utilization of High Performance Computing
Paul Turinsky

 

High Performance Computing in Nuclear Systems: Lessons Learned from Some Recent LWR Applications
Thomas Downar

 

 

 

Parallel Oral Session 9A: Computational Reactor Physics and Particle Transport: Sensitivity, Perturbations, and Optimization

 

New Maximum keff Search Options for "SMORES"
Y. Karni, E. Greenspan

 

Stochastic Finite-Element Approximation of the Parametric Dependence of Eigenvalue Problem Solution
Mihai Anitescu, Giuseppe Palmiotti, Won-Sik Yang, Monika Neda

 

Nonlinear Reactor Control Using the Power Derivative in Feedback and Multiple Time-Scale Analysis
James Paul Holloway

 

Development of Higher-Order Perturbation Approaches Based on Adaptive Euler-Lagrange Fields
Rene van Geemert

 

Using the Levenberg-Marquardt Method for the Solution of Inverse Transport Problems with Scattering
Keith C. Bledsoe, Jeffrey A. Favorite

 

 

 

Parallel Oral Session 9B: Computational Reactor Physics and Particle Transport: Stochastic Considerations in Particle Transport I

 

A Derivation of Akcasu's "MLP" Equations for 1-D Particle Transport in Stochastic Media
Edward W. Larsen, Anil K. Prinja

 

A Critique of the Modified Levermore-Pomraning Model
Richard Sanchez

 

Mean Propagation Kernels for Transport in Correlated Stochastic Media at Unresolved Scales, Illustration with a Problem in Atmospheric Radiation
Anthony Davis

 

A Generalized Boltzmann Equation for "Non-Classical" Particle Transport
Edward W. Larsen

 

Stochastic Averaging of Cross Section Uncertainty in Transport
Anil K. Prinja, Erin D. Fichtl

 

 

 

Parallel Oral Session 9C: Computational Methods in the Nuclear Fuel Cycle

 

A Challenge for Computing in the 21st Century: Radwaste Knowledge Management
Hiroyuki Umeki

 

Radionuclide Transport Calculations from High-Level Long-Lived Radioactive Waste Disposal in Deep Clayed Geologic Formation Toward Adjacent Aquifers
Alain Genty, Christophe Le Potier

 

High Performance FVFE Multidomain Numerical Method to Perform Radionuclides Transport Calculations
M. Dymitrowska, M. Bourgeois, G. Mathieu

 

Uncertainty Analysis of Multiple Canister Repository Model by Large-Scale Calculation
Keiichi Tsujimoto, Hiroshi Okuda, Joonhong Ahn

 

Sensitivity of Repository Thermal-Hydrological-Chemical Simulations to Choice of Numerical Algorithm
S.L. Painter, J. Myers, L. Sabido, A. Sun

 

 

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Parallel Oral Session 10A: Computational Reactor Physics and Particle Transport: Analytical Benchmarks

 

The Analytical Benchmark Library for Nuclear Engineering Applications (Case Studies in Neutron Transport Theory)
Barry Ganapol

 

Parallel PENTRAN Solutions of the "TIEL" Steady State Neutron Transport Benchmark Problems
M. Ghita, G.E. Sjoden, G. Ghita

 

Matrix Albedo for Discrete Ordinates Infinite-Medium Boundary Condition
Kirk Matthews, James Dishaw

 

Verification of the Coupled Space-Angle Adaptivity Algorithm for the Finite Element-Spherical Harmonics Method Via the Method of Manufactured Solutions
Hyeong Kae Park, Cassiano R. E. de Oliveira

 

An Embedded Semi-Analytical Benchmark Via Iterative Interpolation for Neutron Transport Methods Verification
B.D. Ganapol, K.T. Clarno, Seth Johnson, Cassiano de Oliveira, Steven Hamilton

 

 

 

Parallel Oral Session 10B: Computational Reactor Physics and Particle Transport: Stochastic Considerations in Particle Transport II

 

Joint Moments of Neutron Number and Medium State in a Time-Varying Multiplying Medium
Yasunori Kitamura, Imre Pazsit, Akio Yamamoto, Yoshihiro Yamane

 

Calculation of the Pulse Height Distribution Induced by Fast Neutrons in a Scintillation Detector
Andreas Enqvist, Imre Pazsit, Sara Pozzi

 

Monte Carlo Simulation of VHTR Particle Fuel with Chord Length Sampling
Wei Ji, William R. Martin

 

Randomly Dispersed Particle Fuel Model in the PSG Monte Carlo Neutron Transport Code
Jaakko Leppanen

 

Stochastic Geometry in PRIZMA Code
G.N. Malyshkin, E.A. Kashaeva, R.F. Mukhamadiev

 

 

 

Parallel Oral Session 10C: Numerical Methods and Software Architecture for Multiphysics Simulations

 

An Overview of Mesh Generation Technology Applied to Reactor Core Analysis
Glen Hansen

 

Application of High-Order Implicit Schemes for Nonlinear Multi-Physics Simulations
Vijay Mahadevan, Jean Ragusa

 

Implicit Monte Carlo Methods for Coupled Three-Temperatures Transport
T.M. Evans, J.D. Densmore

 

LWR Multi-Physics Developments and Applications Within the Framework of the NURESIM European Project
O. Zerkak, P. Coddington, N. Crouzet, E. Royer, J. Jiminez, D. Cuervo

 

The PCICE Algorithm Coupled with Implicit Conjugate Heat Transfer for Reactor Simulations
Richard Martineau

 

Shock Wave Solutions for Radiation Hydrodynamics
Robert B. Lowrie, Jarrod D. Edwards

 

 

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