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

 

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Ibarra, Lander
A One and Two Dimensional PCICE Based Multiphysics Algorithm for Use in Reactor Core Calculations 

Insepov, Z.
Computer Simulation of Bubble Formation  

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

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

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

Jessee, Matthew A.
Evaluation of BWR Core Attributes Uncertainties due to Multigroup Cross Section Uncertainties 

Interpolation Methods and Splice Options for Three-Dimensional Transport Calculations Using Partisn 

Ji, Wei
Monte Carlo Simulation of VHTR Particle Fuel with Chord Length Sampling  

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

Johnson, Seth
An Embedded Semi-Analytical Benchmark Via Iterative Interpolation for Neutron Transport Methods Verification  

Joo, H.
The MC21 Monte Carlo Transport Code  

Joo, H. K.
Application of Nodal Equivalence Parameters for Prismatic VHTR Core Analysis  

Joo, Han Gyu
Generation of Subgroup Weights Employing Shielded Cross Section Conservation Principle for Representative Pin Cells  

Joo, Hyung-Kook
VHTR Numerical Benchmark Based on the Compact Nuclear Power Source Experiments  

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

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

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

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

Kandiev, Y.Z.
Simulation of Electron and Photon Transport Through Tumorous and Surrounding Tissues with 3D Monte Carlo Codes  

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

Kashaeva, E.A.
Stochastic Geometry in PRIZMA Code  

Kaushik, D.
PNFE Component of the UNIC Code  

UNIC: Ultimate Neutronic Investigation Code  

Software Design of SHARP  

Kawasaki, K.
A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure  

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

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

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

Khotylev, Vladimir A.
Generation of Multi-Group Cross Sections and Scattering Matrices with the Monte Carlo Code MCNP5 

Kim, Chang Hyo
Generation of Subgroup Weights Employing Shielded Cross Section Conservation Principle for Representative Pin Cells 

Kim, Kang Seog
Generation of Subgroup Weights Employing Shielded Cross Section Conservation Principle for Representative Pin Cells  

Comparison of Two-Step Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR-400 Problem  

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

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

Kitamura, Yasunori
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  

Klaver, P.
Stability of Uncommon Interstitials in Fe  

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

Kloosterman, J.L.
Mechanical Stresses in Fuel Particles and Graphite of High Temperature Reactors  

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

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

Kochunas, B.
Improved Parallelization of the Modular Ray Tracing in the Method of Characteristics Code DeCart  

Axial Dependence of Homogenized Cross Sections Used for Nodal Analysis of the Boiling Water Reactor  

Koga, James
Computational Physics of Photon Science  

High Power Gamma Ray Source by Radiation Damping  

Kosheleva, E. V.
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  

Kramer, Kevin
Osiris: A Modern, High-Performance, Coupled, Multi-Physics Code For Nuclear Reactor Core Analysis  

Kramer, Kevin
New Capabilities in Mercury: A Modern Monte Carlo Particle Transport Code  

Kuijper, J. C.
Using Homogenized Macroscopic Group Cross Sections in Continuous-Energy Monte Carlo Neutron Transport Calculations with MCNP  

Kushida, N.
A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure  

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

High Accuracy Large Scale Monte Carlo and Deterministic Transport Calculations for Critical Systems 

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

A Derivation of Akcasu's "MLP" Equations for 1-D Particle Transport in Stochastic Media  

A Generalized Boltzmann Equation for "Non-Classical" Particle Transport  

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

Lautard, J. J.
Unstructured 3D Core Calculations with the Descartes System: Application to the JHR Research Reactor  

A Multi-Scale Approach for the Neutronic Kinetics Equations Using the Mixed Dual Solver MINOS  

Domain Decomposition Methods for Core Calculations Using the MINOS Solver  

Laval, V.
Full MOX ABWR Neutron Characterization with Void Increase: The FUBILA Program  

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

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

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

Leclere, M.
UNIC: Ultimate Neutronic Investigation Code  

Lee, C.H.
Application of Nodal Equivalence Parameters for Prismatic VHTR Core Analysis  

Lee, Hyun Chul
Comparison of Two-Step Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR-400 Problem  

Lee, John C.
Degradation Monitoring in IRIS Steam Generators  

Lee, Young-Seok
Doppler Coefficient of Reactivity - Benchmark Calculations for Different Enrichments of UO2  

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

Lewis, E. E.
PNFE Component of the UNIC Code  

UNIC: Ultimate Neutronic Investigation Code  

A New Paradigm for Whole Core Neutron Transport Without Homogenization  

Litaize, O.
New Modelling of LWR Assemblies Using the Apollo2 Code Package  

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

Lockwood, Brian
A One and Two Dimensional PCICE Based Multiphysics Algorithm for Use in Reactor Core Calculations 

Lottes, James
Large Eddy Simulation of Wire Wrapped Fuel Pins I: Hydrodynamics in a Periodic Array  

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

Lowrie, Robert B.
Shock Wave Solutions for Radiation Hydrodynamics  

Lozano, Juan-Andres
Development and Performance of the Analytic Nodal Diffusion Solver "ANDES" in Multigroups for 3D Rectangular Geometry  

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

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

Maiorino, J.R.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems  

Malakhov, A.A.
Simulation of Electron and Photon Transport Through Tumorous and Surrounding Tissues with 3D Monte Carlo Codes  

Malerba, L.
Stability of Uncommon Interstitials in Fe  

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

Malyshkin, G.N.
Stochastic Geometry in PRIZMA Code  

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

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

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

Martin-del-Campo, C.
Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms  

LPPF Prediction in a BWR Fuel Lattice Using Artificial Neural Networks  

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

Matsubara, H.
A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure  

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

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

A P1 Benchmark for Time Dependent Thermal Radiative Transfer  

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

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

Merk, Stephan
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

Mihalczo, John
Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation  

Miller, G.K.
Mechanical Stresses in Fuel Particles and Graphite of High Temperature Reactors  

Milosevic, Miodrag
TRITON/NEWT Calculation of the CORAIL Assembly for Plutonium Recycling in PWR  

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

Miró, R.
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  

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

Mohseni, Niloofar
A New Strategy for Optimal Fuel Core Loading Pattern Design in PWR Nuclear Power Reactors  

Mondelain, Laure
Use of the APOLLO2 Code for BWR Assembly Analysis  

Montes, Jose L.
LPPF Prediction in a BWR Fuel Lattice Using Artificial Neural Networks  

Moreau, Frederic
Unstructured 3D Core Calculations with the Descartes System: Application to the JHR Research Reactor  

Morel, Jim E.
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  

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

Morrow, R. E.
A k-eff Search Capability in MC21  

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

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

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

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

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

Mukhamadiev, R. F.
Stochastic Geometry in PRIZMA Code  

Nachaoui, A.
A Multi-Scale Approach for the Neutronic Kinetics Equations Using the Mixed Dual Solver MINOS  

Nakajima, N.
A Methodology of Structural Analysis for Nuclear Power Plant Size of Assembly Structure  

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

Nease, Brian
Information Criteria and Higher Eigenmode Estimation in Monte Carlo Calculations  

Convergence Testing for MCNP5 Monte Carlo Eigenvalue Calculations  

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

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

Nicolino, C.
Reactivity Oscillations in Molten Salt Reactors  

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

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

Noh, Jae Man
Comparison of Two-Step Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR-400 Problem  

Norman, G.
Computer Simulation of Bubble Formation  

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

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

O'Brien, Matthew
New Capabilities in Mercury: A Modern Monte Carlo Particle Transport Code  

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

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

Okuda, Hiroshi
Uncertainty Analysis of Multiple Canister Repository Model by Large-Scale Calculation  

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

Oropeza, I.P.
Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms  

Ortiz, Juan J.
LPPF Prediction in a BWR Fuel Lattice Using Artificial Neural Networks  

Otobe, Tomohito
Computational Physics of Photon Science  

Ougouag, A.M.
Mechanical Stresses in Fuel Particles and Graphite of High Temperature Reactors  

Earthquakes and Pebble Bed Reactors: Time-Dependent Densification  

Padovani, Enrico
Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation  

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

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

Palmiotti, G.
PNFE Component of the UNIC Code  

UNIC: Ultimate Neutronic Investigation Code  

A New Paradigm for Whole Core Neutron Transport Without Homogenization  

Software Design of SHARP  

Palmiotti, Giuseppe
Large Eddy Simulation of Wire Wrapped Fuel Pins I: Hydrodynamics in a Periodic Array  

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

Palomera, M.A.
Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms  

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

Park, Hyeong Kae
Verification of the Coupled Space-Angle Adaptivity Algorithm for the Finite Element-Spherical Harmonics Method Via the Method of Manufactured Solutions  

Parsons, Dennis
Osiris: A Modern, High-Performance, Coupled, Multi-Physics Code For Nuclear Reactor Core Analysis  

Pattnaik, Aliva
Load Balancing Strategy for Radiation Transport Code EVENT  

Pautz, Andreas
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

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

Monte Carlo Models of Neutron Detection with Organic Scintillators  

Analytical and Numerical Modelling of the Detection Statistics of Emission from a Fissile Sample with Absorption  

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

Calculation of the Pulse Height Distribution Induced by Fast Neutrons in a Scintillation Detector  

Peterson, P.F.
The Multi-Physics User-Friendly Gas-Dynamics Code Visual Tsunami 2.0  

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

Platonova, L.A.
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  

Pogosbekyan, Leonid
Generation of Subgroup Weights Employing Shielded Cross Section Conservation Principle for Representative Pin Cells  

Pointer, W. D.
Coupled BWR Calculations with the Numerical Nuclear Reactor Software System  

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

Pothet, Baptiste
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

Pounders, Justin
Flux-Limited Diffusion Coefficients in Reactor Physics Applications  

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

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

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

Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation  

Monte Carlo Models of Neutron Detection with Organic Scintillators 

Analytical and Numerical Modelling of the Detection Statistics of Emission from a Fissile Sample with Absorption 

Calculation of the Pulse Height Distribution Induced by Fast Neutrons in a Scintillation Detector 

Prinja, Anil K.
A New Electron Energy-Loss Straggling Algorithm in MCNP  

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

Subcell SN Sweeping for Meshes with Reentrant Cells  

A Derivation of Akcasu's "MLP" Equations for 1-D Particle Transport in Stochastic Media  

Stochastic Averaging of Cross Section Uncertainty in Transport  

Prinsloo, Rian
Cross-Section Parameterization Using Quasi-Regression Approach  

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

Procassini, Richard
Osiris: A Modern, High-Performance, Coupled, Multi-Physics Code For Nuclear Reactor Core Analysis  

A Monte Carlo Method for Calculating Initiation Probability  

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

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

Punin, V.T.
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  

 

 

 

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