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

 

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Abdel-Khalik, Hany S.
Evaluation of BWR Core Attributes Uncertainties due to Multigroup Cross Section Uncertainties  

Ahn, Joonhong
Uncertainty Analysis of Multiple Canister Repository Model by Large-Scale Calculation  

Ahnert, Carol
3D Whole Core Fine Mesh Multigroup Diffusion Calculations by Domain Decomposition Through Alternate Dissections  

Alpay, Bulent
Degradation Monitoring in IRIS Steam Generators  

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

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

Analysis of the Quasidiffusion Method on Two-Dimensional Problems with Spatially Periodic Media  

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

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

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

Aragonés, José M.
3D Whole Core Fine Mesh Multigroup Diffusion Calculations by Domain Decomposition Through Alternate Dissections  

Development and Performance of the Analytic Nodal Diffusion Solver "ANDES" in Multigroups for 3D Rectangular Geometry  

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

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

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

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

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

Baudron, A.M.
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  

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

Bazhirov, T.
Computer Simulation of Bubble Formation  

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

Bellanger, Veronique
Use of the APOLLO2 Code for BWR Assembly Analysis  

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

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

Bernard, D.
New Modelling of LWR Assemblies Using the Apollo2 Code Package  

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

Blaise, P.
Full MOX ABWR Neutron Characterization with Void Increase: The FUBILA Program  

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

Boer, B.
Mechanical Stresses in Fuel Particles and Graphite of High Temperature Reactors  

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

Bolloni, Hans-Wilhelm
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

Bonneau, F.
A Numerical Investigation of the LLNL/AWE/CEA Fragmentation Experiments on HELEN  

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

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

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

Reconstruction of the Local Neutron-Physical Functionals in Surface Harmonics Method  

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

Monte Carlo Particle Transport Capability for Inertial Confinement Fusion Applications  

Breith, Karl-Albert
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

Brown, Forrest
Wielandt Acceleration for MCNP5 Monte Carlo Eigenvalue Calculations  

Convergence Testing for MCNP5 Monte Carlo Eigenvalue Calculations  

Brunner, Thomas A.
A P1 Benchmark for Time Dependent Thermal Radiative Transfer  

Buksas, Michael W.
A Hybrid Monte Carlo-Diffusion Method for Radiation Transport on Adaptive Mesh Refinement-Type Meshes  

Bulanov, Sergei
Computational Physics of Photon Science  

Caceres, A.
Software Design of SHARP  

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

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

Carluccio, T.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems  

Carmona, R.
Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms  

Caro, E.
The MC21 Monte Carlo Transport Code  

Carpenter, D.C.
The MC21 Monte Carlo Transport Code  

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

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

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

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

Cheatham, Jesse
Convergence Testing for MCNP5 Monte Carlo Eigenvalue Calculations  

Chernov, V.M.
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  

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

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

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

Christoforou, Stavros
Transition and Collision Biasing in a Variance Reduction Scheme for Criticality Calculations  

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

Clarke, Shaun
Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation  

Clarno, K.T.
An Embedded Semi-Analytical Benchmark Via Iterative Interpolation for Neutron Transport Methods Verification  

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

A Monte Carlo Method for Calculating Initiation Probability  

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

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

Combis, P.
A Numerical Investigation of the LLNL/AWE/CEA Fragmentation Experiments on HELEN  

Conlin, Jeremy L.
Computational Benchmark of the Doppler Reactivity Defect  

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

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

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

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

Curca-Tivig, Florin
The ARTEMIS Core Simulator: A Central Component in AREVA NP's Code Convergence Project  

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

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

Davis, J.E.
Converting Boundary-Representation Solid Models to Half-Space Representation Models for Monte Carlo Analysis  

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

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

Load Balancing Strategy for Radiation Transport Code EVENT 

A Populational Particle Collision Algorithm Applied to a Nuclear Reactor Core Design Optimization 

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

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

de Oliveira, F.
Analytical Benchmarks for the Kinetics of Accelerator-Driven Systems 

Debonnel, C.S.
A Numerical Investigation of the LLNL/AWE/CEA Fragmentation Experiments on HELEN  

The Multi-Physics User-Friendly Gas-Dynamics Code Visual Tsunami 2.0  

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

Simplification of Multi-Group Cross-Section Processing for Large Depletion Calculations in TRITON  

KENO Continuous Energy Calculations for a Suite of Computational Benchmarks for the Doppler Reactivity Defect  

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

Calculation of the Eigenfunctions and Corresponding Eigenvalues of the Two-Group Diffusion Equation in Heterogeneous Systems  

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

Densmore, J. D.
A Fokker-Planck Method for Modeling Compton Scattering in Implicit Monte Carlo Simulations  

A Hybrid Monte Carlo-Diffusion Method for Radiation Transport on Adaptive Mesh Refinement-Type Meshes  

Implicit Monte Carlo Methods for Coupled Three-Temperatures Transport  

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

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

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

Do, Jean Michel
Use of the APOLLO2 Code for BWR Assembly Analysis  

Dobreff, P.S.
The MC21 Monte Carlo Transport Code  

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

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

Donovan, T. J.
The MC21 Monte Carlo Transport Code  

A k-eff Search Capability in MC21  

Downar, T. J.
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  

Optimal Perturbation Size for Matrix Free Newton/Krylov Methods  

The Calculation of Resonance Parameters for the DeCART MOC Code  

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

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  

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

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

Reactivity Oscillations in Molten Salt Reactors  

Dunn, Michael E.
KENO Continuous Energy Calculations for a Suite of Computational Benchmarks for the Doppler Reactivity Defect  

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

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

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

Edwards, Jarrod D.
Shock Wave Solutions for Radiation Hydrodynamics  

Enqvist, Andreas
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  

Esirkepov, Timur
Computational Physics of Photon Science  

Evans, T. M.
A Hybrid Monte Carlo-Diffusion Method for Radiation Transport on Adaptive Mesh Refinement-Type Meshes  

Implicit Monte Carlo Methods for Coupled Three-Temperatures Transport  

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

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

Fevotte, Francois
Advanced Transverse Integration for the Method of Characteristics  

Fichtl, Erin D.
Krylov Iterative Methods and Synthetic Acceleration for Transport in Binary Statistical Media  

Stochastic Averaging of Cross Section Uncertainty in Transport  

Filho, Hermes Alves
A Populational Particle Collision Algorithm Applied to a Nuclear Reactor Core Design Optimization  

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

Software Design of SHARP  

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

Flaska, Marek
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  

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

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

Fougeras, P.
Full MOX ABWR Neutron Characterization with Void Increase: The FUBILA Program  

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

François, J. L.
LPPF Prediction in a BWR Fuel Lattice Using Artificial Neural Networks  

Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms  

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

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

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

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

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

Ganda, Francesco
TRITON/NEWT Calculation of the CORAIL Assembly for Plutonium Recycling in PWR  

Gandini, Augusto
Investigations on the Migration Mode Method (MMM) for Reactor Calculations  

Gao, Zhenjia
The Calculation of Resonance Parameters for the DeCART MOC Code  

García-Herranz, Nuria
Development and Performance of the Analytic Nodal Diffusion Solver "ANDES" in Multigroups for 3D Rectangular Geometry  

Gauld, Ian C.
High-Fidelity Lattice Physics Capabilities of the SCALE Code System Using TRITON  

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

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

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

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

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

Ghoniem, Nasr M.
The Motion of Dislocations in Irradiated Materials  

Glass, C.
Axial Dependence of Homogenized Cross Sections Used for Nodal Analysis of the Boiling Water Reactor  

Gleicher, Frederick N.
Subcell SN Sweeping for Meshes with Reentrant Cells  

Goluoglu, Sedat
KENO Continuous Energy Calculations for a Suite of Computational Benchmarks for the Doppler Reactivity Defect  

Gonnord, Jean
Europe Back in HPC World  

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

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

Grasso, G.
PIC-MCC Simulation of the Electrical Breakdown in a Plasma Focus Device  

Greenman, Gregory
A Monte Carlo Method for Calculating Initiation Probability  

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

Greenspan, E.
TRITON/NEWT Calculation of the CORAIL Assembly for Plutonium Recycling in PWR  

Determination of the Equilibrium Composition of Cores with Continuous Fuel Feed and Removal Using MOCUP  

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

New Maximum keff Search Options for "SMORES"  

Griesheimer, D. P.
A Novel Source Convergence Acceleration Scheme for Monte Carlo Criticality Calculations, Part I: Theory  

The MC21 Monte Carlo Transport Code  

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

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

Guerin, Pierre
Domain Decomposition Methods for Core Calculations Using the MINOS Solver  

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

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

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

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

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

Hamilton, Steven
An Embedded Semi-Analytical Benchmark Via Iterative Interpolation for Neutron Transport Methods Verification  

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

Harding, Lee T.
A New Electron Energy-Loss Straggling Algorithm in MCNP  

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

Hauser, Eliete Biasotto
The LTSN Exponential Nodal Method for One-Speed XY-Geometry Discrete Ordinates Problems in Heterogeneous Media  

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

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

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

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

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

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

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

Hogenbirk, A.
Using Homogenized Macroscopic Group Cross Sections in Continuous-Energy Monte Carlo Neutron Transport Calculations with MCNP  

An Easy Way to Carry Out 3D Uncertainty Analyses  

Holloway, James Paul
High Resolution Time Integration for the Spherical Harmonics Equations  

A P1 Benchmark for Time Dependent Thermal Radiative Transfer  

Degradation Monitoring in IRIS Steam Generators  

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

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

Analytical Solution of a Simplified Transport Problem with Continuous Energy for Testing Monte Carlo Procedures 

Generation of Multi-Group Cross Sections and Scattering Matrices with the Monte Carlo Code MCNP5 

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

Hughes, H. Grady
A New Electron Energy-Loss Straggling Algorithm in MCNP  

Hunt, Alan
Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation  

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

Hursin, M.
Axial Dependence of Homogenized Cross Sections Used for Nodal Analysis of the Boiling Water Reactor  

 

 

 

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