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

 

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Author Index (for Papers on the CD)

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Rabiti, C.
PNFE Component of the UNIC Code  

Rabiti, C.
UNIC: Ultimate Neutronic Investigation Code  

Ragusa, J.
Goal-Oriented hp-Mesh Adaptation for 1-D Multigroup Diffusion Equations  

Software Design of SHARP  

Multi-Dimensional Automatic Mesh Refinement for the Multigroup SPN Equations  

Application of High-Order Implicit Schemes for Nonlinear Multi-Physics Simulations  

Rahnema, Farzad
Flux-Limited Diffusion Coefficients in Reactor Physics Applications  

Evaluation of a Heterogeneous Coarse Mesh Photon Transport Method Using a Simplified Lung Model  

Raji, Mohammad H.
A New Strategy for Optimal Fuel Core Loading Pattern Design in PWR Nuclear Power Reactors  

Ravetto, P.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems  

Reactivity Oscillations in Molten Salt Reactors  

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

Simulation of Chaotic ABC Flow Using Parallel Modified Nodal Integral Method  

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

Rocchi, F.
PIC-MCC Simulation of the Electrical Breakdown in a Plasma Focus Device  

Roche, A.
Full MOX ABWR Neutron Characterization with Void Increase: The FUBILA Program  

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

Rosa, Massimiliano
Fourier Analysis of Parallel Block-Jacobi Splitting with Transport Synthetic Acceleration in Two-Dimensional Geometry  

Rotella, Rossella
Investigations on the Migration Mode Method (MMM) for Reactor Calculations  

Royer, E.
LWR Multi-Physics Developments and Applications Within the Framework of the NURESIM European Project  

Sacco, Wagner F.
A Populational Particle Collision Algorithm Applied to a Nuclear Reactor Core Design Optimization  

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

Samarin, S.I.
Simulation of Electron and Photon Transport Through Tumorous and Surrounding Tissues with 3D Monte Carlo Codes  

Sanchez, Richard
Advanced Transverse Integration for the Method of Characteristics  

A Critique of the Modified Levermore-Pomraning Model  

Santamarina, A.
New Modelling of LWR Assemblies Using the Apollo2 Code Package  

Santandrea, Simone
Advanced Transverse Integration for the Method of Characteristics 

An Unstructured Characteristics Scheme with a Linear Expansion for Both Fluxes and Cross Sections

Santos, A.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems  

Santos, R.S.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems  

Satterfield, Megan
Evaluation of a Heterogeneous Coarse Mesh Photon Transport Method Using a Simplified Lung Model  

Sayeed, Mohamed
Improved Parallelization of the Modular Ray Tracing in the Method of Characteristics Code DeCart  

Seker, Volkan
Reactor Simulation with Coupled Monte Carlo and Computational Fluid Dynamics  

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

Selchenkova, N.I.
Materials in Extreme Conditions the Critical Phenomena and Phase Transfer in the Dynamic Destruction  

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  

Serova, E.V.
Simulation of Electron and Photon Transport Through Tumorous and Surrounding Tissues with 3D Monte Carlo Codes  

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

Siegel, A.
Large Eddy Simulation of Wire Wrapped Fuel Pins I: Hydrodynamics in a Periodic Array  

PNFE Component of the UNIC Code  

UNIC: Ultimate Neutronic Investigation Code  

Software Design of SHARP  

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

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

Energetic, Kinetic and Crystallographic Characteristics of Self-Point Defects in Vanadium and Iron Crystals  

Self-Point Defects Characteristics and Their Dependence on <1120> {0001} Dislocation Stress Field in Alpha-Zr  

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

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

Smith, B.
PNFE Component of the UNIC Code  

UNIC: Ultimate Neutronic Investigation Code  

Smith, M.
UNIC: Ultimate Neutronic Investigation Code  

Software Design of SHARP  

Smith, M.A.
PNFE Component of the UNIC Code  

A New Paradigm for Whole Core Neutron Transport Without Homogenization  

Sofu, T.
Coupled BWR Calculations with the Numerical Nuclear Reactor Software System  

Eulerian Two-Phase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis  

Spirina, S.G.
Simulation of Electron and Photon Transport Through Tumorous and Surrounding Tissues with 3D Monte Carlo Codes  

Splawski, Andrew
Eulerian Two-Phase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis  

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

Stegailov, V.
Computer Simulation of Bubble Formation  

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

Subbaiah, K.V.
Doppler Coefficient of Reactivity - Benchmark Calculations for Different Enrichments of UO2  

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

Sumini, M.
PIC-MCC Simulation of the Electrical Breakdown in a Plasma Focus Device  

Sun, Mingshan
The Use of Monte Carlo Simulation in Improving Reconstruction Quality in Single Photon Emission Computed Tomography  

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

Investigation of the Validity of the Point-Kinetic Approximation and of the Break-Frequency Method in 2-D Subcritical Systems  

Sunny, C. Sunil
Doppler Coefficient of Reactivity - Benchmark Calculations for Different Enrichments of UO2  

Sutton, T.M.
Converting Boundary-Representation Solid Models to Half-Space Representation Models for Monte Carlo Analysis  

The MC21 Monte Carlo Transport Code  

A k-eff Search Capability in MC21  

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

Suzuki, Y.
A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure  

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

Szilard, Ronaldo
Flux-Limited Diffusion Coefficients in Reactor Physics Applications  

Tada, Kenichi
Performance of the Diffusion and Simplified PN Theories for BWR Pin-by-Pin Fine Mesh Core Analyses 

Taiwo, T. A.
TRITON/NEWT Calculation of the CORAIL Assembly for Plutonium Recycling in PWR  

VHTR Numerical Benchmark Based on the Compact Nuclear Power Source Experiments  

Application of Nodal Equivalence Parameters for Prismatic VHTR Core Analysis  

Neutronics Assessment of Stringer Fuel Assembly Designs for the Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR)  

Tajima, Toshiki
Computational Physics of Photon Science  

Takahashi, Akiyuki
The Motion of Dislocations in Irradiated Materials  

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

Tani, M.
A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure  

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

Tautges, T.
Software Design of SHARP  

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

Taylor, Janine
New Capabilities in Mercury: A Modern Monte Carlo Particle Transport Code  

Tentner, Adrian
Eulerian Two-Phase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis  

Terentyev, D.
Stability of Uncommon Interstitials in Fe  

Stability and Mobility of Self-Interstitial Atoms and their Clusters in Fe-Cr Alloys: An Atomic-Level Study  

Thilagam, L.
Doppler Coefficient of Reactivity - Benchmark Calculations for Different Enrichments of UO2  

Thiollay, N.
Full MOX ABWR Neutron Characterization with Void Increase: The FUBILA Program  

Tholammakkil, John M.
Generation of Multi-Group Cross Sections and Scattering Matrices with the Monte Carlo Code MCNP5 

Thomas, J. W.
Reactor Simulation with Coupled Monte Carlo and Computational Fluid Dynamics  

Coupled BWR Calculations with the Numerical Nuclear Reactor Software System  

Improved Parallelization of the Modular Ray Tracing in the Method of Characteristics Code DeCart  

Tobin, J.G.
Experimental Benchmarking of Pu Electronic Structure  

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

Tomatis, D.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems  

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

A Novel Source Convergence Acceleration Scheme for Monte Carlo Criticality Calculations, Part II: Implementation and Results  

Tran, R.
New Modelling of LWR Assemblies Using the Apollo2 Code Package  

Trubov, L.
The Multi-Physics User-Friendly Gas-Dynamics Code Visual Tsunami 2.0  

Trumbull, T.H.
The MC21 Monte Carlo Transport Code  

A k-eff Search Capability in MC21  

Tsujimoto, Keiichi
Uncertainty Analysis of Multiple Canister Repository Model by Large-Scale Calculation  

Turinsky, Paul J.
Evaluation of BWR Core Attributes Uncertainties due to Multigroup Cross Section Uncertainties  

Tyburski, L.J.
The MC21 Monte Carlo Transport Code  

Uchaev, A.Ya.
Materials in Extreme Conditions the Critical Phenomena and Phase Transfer in the Dynamic Destruction  

Uchaev, A.Ya.
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  

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

Ueki, Taro
Information Criteria and Higher Eigenmode Estimation in Monte Carlo Calculations  

Particle Population Diagnostics in Iterated-Source Monte Carlo Methods  

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

Vaglio-Gaudard, C.
New Modelling of LWR Assemblies Using the Apollo2 Code Package  

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

van Geemert, Rene
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

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

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

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

Velkov, K.
Experiences Applying Unicore Grid Middleware for Nuclear Simulation Tools Like the 3D Reactor Core Model QUABOX/CUBBOX  

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

Verboomen, Bernard
Feasibility of Using a Universal Point Wise Energy Grid or a Very Fine Multi-Group Energy Grid in MORET5 Criticality Calculations  

Verdú, G.
Monte Carlo Modeling of the Elekta Precise Linear Accelerator: Validation of Dose Distribution in a Heterogeneous Water Phantom  

Some Experiments Using Preconditioning Techniques and Second-Order Iterative Methods for the Resolution of the 3D Transient Neutron Diffusion Equation  

Vidal, J.F.
New Modelling of LWR Assemblies Using the Apollo2 Code Package  

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

Vierne, J.L.
A Numerical Investigation of the LLNL/AWE/CEA Fragmentation Experiments on HELEN  

Vilhena, Marco Tullio
The LTSN Exponential Nodal Method for One-Speed XY-Geometry Discrete Ordinates Problems in Heterogeneous Media  

Vujic, J.
Benchmarking of Monte Carlo Simulations of Thermal Neutron Kinetics and Differential Die-Away Analysis  

The Use of Monte Carlo Simulation in Improving Reconstruction Quality in Single Photon Emission Computed Tomography  

Effects of Uncertainties in Lead Cross Section Data in Monte Carlo Analysis of Lead Cooled and Reflected Reactors  

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

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

Multi-Dimensional Automatic Mesh Refinement for the Multigroup SPN Equations  

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

Krylov Iterative Methods and Synthetic Acceleration for Transport in Binary Statistical Media  

Subcell SN Sweeping for Meshes with Reentrant Cells  

Solution Algorithms for a PN-1-Equivalent SN Angular Discretization of the Transport Equation in One-Dimensional Spherical Coordinates  

A Fokker-Planck Method for Modeling Compton Scattering in Implicit Monte Carlo Simulations  

Fourier Analysis of Parallel Block-Jacobi Splitting with Transport Synthetic Acceleration in Two-Dimensional Geometry  

Watanabe, Masato
Performance of the Diffusion and Simplified PN Theories for BWR Pin-by-Pin Fine Mesh Core Analyses 

Weber, D.P.
Coupled BWR Calculations with the Numerical Nuclear Reactor Software System  

Weber, David
Eulerian Two-Phase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis  

Wen, Ming
The Motion of Dislocations in Irradiated Materials  

Willaime, F.
Stability of Uncommon Interstitials in Fe  

Williams, Mark L.
High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON  

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

Xu, Yunlin
Optimal Perturbation Size for Matrix Free Newton/Krylov Methods  

The Calculation of Resonance Parameters for the DeCART MOC Code  

A Sequential Least Squares Algorithm for Neutron Spectrum Unfolding from Pulse-Height Distributions Measured with Liquid Scintillators  

Yamagiwa, Mitsuru
Computational Physics of Photon Science  

High Power Gamma Ray Source by Radiation Damping  

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

Yamamoto, Akio
Performance of the Diffusion and Simplified PN Theories for BWR Pin-by-Pin Fine Mesh Core Analyses 

Joint Moments of Neutron Number and Medium State in a Time-Varying Multiplying Medium 

Yamane, Yoshihiro
Performance of the Diffusion and Simplified PN Theories for BWR Pin-by-Pin Fine Mesh Core Analyses 

Joint Moments of Neutron Number and Medium State in a Time-Varying Multiplying Medium 

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

Yang, W. S.
Application of Nodal Equivalence Parameters for Prismatic VHTR Core Analysis  

Yang, Won Sik
VHTR Numerical Benchmark Based on the Compact Nuclear Power Source Experiments  

Stochastic Finite-Element Approximation of the Parametric Dependence of Eigenvalue Problem Solution  

Yehnert, Carl E.
Interpolation Methods and Splice Options for Three-Dimensional Transport Calculations Using Partisn 

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

Yilmazbayhan, Aylin
Radiation Interaction Analysis for BWR Channel Shadow Corrosion  

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

Zeballos, C.A.
The Multi-Physics User-Friendly Gas-Dynamics Code Visual Tsunami 2.0  

Zerkak, O.
LWR Multi-Physics Developments and Applications Within the Framework of the NURESIM European Project  

Zhang, Dingkang
Evaluation of a Heterogeneous Coarse Mesh Photon Transport Method Using a Simplified Lung Model  

Zhong, Z.
Application of Nodal Equivalence Parameters for Prismatic VHTR Core Analysis  

Zmijarevic, Igor
Use of the APOLLO2 Code for BWR Assembly Analysis  

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

 

 

 

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