May 3-7, 2009 ~ SARATOGA SPRINGS, NY, USA

 

 

 

Author Index (for Papers on the CD)

 

 

 

Abdel-Khalik, Hany S.
Subspace Multi-SCALE Approach for Reactor Analysis, Part I: Energy Variable  

Abramov, Boris Dmitrievich
On Reactivity Effects Calculations  

Adams, Marvin
Scalable Parallel Prefix Solvers for Discrete Ordinates Transport  

Adams, Marvin L.
A Piecewise Linear Discontinuous Finite Element Spatial Discretization of the Transport Equation in 2D Cylindrical Geometry  

Adams, Marvin L.
Semi-Consistent Diffusion Synthetic Acceleration for Discontinuous Discretizations of Transport Problems  

Adams, Marvin L.
Method of Long Characteristics Applied in Space and Time  

Ahnert, Carol
Performance of Whole Core Pin-by-Pin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations  

Al-Basheer, Ahmad
Application of Electron Dose Kernels to Account for Heterogeneities in Voxelized Phantoms  

Al-Basheer, Ahmad
Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications  

Alexandrov, Michael
Inversion of Multi-Angle Radiation Measurements  

Al-Hamry, A.
Development of a Coupling Scheme between MCNP and COBRA-TF for the Prediction of the Pin Power of a PWR Fuel Assembly  

Allelein, H. J.
Monte-Carlo-Based Simulation of LWR Cores with Innovative Fuel Concepts  

Allen, Todd
Determination of Solute-Interstitial Interactions in Ni-Cr by First Principles  

Ambers, Scott
Analytical Description of Pulses Measured with an Organic Liquid Scintillator for Pulse Shape Discrimination  

Anistratov, Dmitriy Y.
Multi-Level Methods for Solving Multigroup Transport Eigenvalue Problems in 1D Slab Geometry  

Anistratov, Dmitriy Y.
A Quasidiffusion Method for Unstructured Quadrilateral Meshes in 2D XY Geometry  

Aoyama, Motoo
Development of Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix  

Aragones, J. M.
Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry  

Aragonés, José-María
Performance of Whole Core Pin-by-Pin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations  

Argaud, Jean-Phillippe
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Arnaud, Gilles
Fuel Loading Pattern for Heterogeneous EPR Core Configuration Using a Distributed Evolutionary Algorithm  

Arreola, Manuel
Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications  

Artioli, Carlo
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: Application to a Generation IV Lead Fast Reactor (LFR)  

Asbury, Stephen
Multi-Grid Genetic Algorithms for Space Shield Design  

Assawaroongruengchot, Monchai
Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+  

Augelli, Mauro
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Avdic, Senada
Combined Use of Neutron and Gamma Multiplicities for Determining Sample Parameters  

Avramova, Maria Nikolova
Uncertainty Analysis of COBRA-TF Void Distribution Predictions for the OECD/NRC BFBT Benchmark  

Avramova, Maria Nikolova
Overview and Discussion of Phase I of the OECD LWR UAM Benchmark Activity  

Avramova, Maria Nikolova
High Accuracy Modeling for Advanced Nuclear Reactor Core Designs Using Monte Carlo Based Coupled Calculations  

Avramova, Maria Nikolova
Verification & Validation and Uncertainty Analysis in Multi-Physics Modeling for Nuclear Reactor Design and Safety  

Azmy, Yousry
A Case Study to Test MOZAIK for Different Optimization Problems  

Azmy, Yousry Youssef
Verification and Validation of Deterministic Radiation Transport Numerical Methods, Codes, and Nuclear Data for Estimating Radiation Dose to Patients During CT Scan  

Azmy, Yousry Youssef
A Robust Arbitrarily High Order Transport Method of the Characteristic Type for Unstructured Tetrahedral Grids  

Azmy, Yousry Youssef
A Jacobian-Free Newton-Krylov Iterative Scheme for Criticality Calculations Based on the Neutron Diffusion Equation  

Azmy, Yousry Youssef
A Parallel Algorithm for Solving the Integral Form of the Discrete Ordinates Equations  

Azmy, Yousry Youssef
Revisiting the TORT Solutions to the NEA Suite of Benchmarks for 3D Transport Methods and Codes over a Range in Parameter Space  

Azmy, Yousry Youssef
On the Adequacy of Cartesian Geometry Discrete Ordinates Solutions for Assembly Calculations  

Baciak, James E.
Assessment of Mark I Rod Irradiations in the UF Subcritical Water Tank Experiment Using Transport Methods  

Bahran, R.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Bahran, Rian
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Bailey, Teresa S.
A Piecewise Linear Discontinuous Finite Element Spatial Discretization of the Transport Equation in 2D Cylindrical Geometry  

Bailey, Teresa S.
Analysis of Massively Parallel Discrete-Ordinates Transport Sweep Algorithms with Collisions  

Baker, Randal S.
Deterministic Methods for Time-Dependent Stochastic Neutron Transport  

Bal, Guillaume
Radiation Transport through Random Media  

Ball, M.
The University of Pisa Calculations for the Phase I of the OECD/NEA UAM Benchmark  

Banerjee, Kaushik
Kernel Density Estimated Monte Carlo Global Flux Tallies  

Baocheng, Zhang
Development of New Pin Power Recovery Methodology  

Baratta, Anthony J.
A Time-Dependent Method of Characteristics for 3D Nuclear Reactor Kinetics Applications  

Barbu, Anthony
Semi-Consistent Diffusion Synthetic Acceleration for Discontinuous Discretizations of Transport Problems  

Barker, Howard W.
On the Application of Monte Carlo Solutions of the Radiative Transfer Equation for Cloudy Terrestrial Atmospheres  

Barrachina, Teresa
Qualification of the TH-3DNK Coupled Code RELAP5/PARCSv2.7 Against a BWR Unstable Point at Peach Bottom Nuclear Power Plant  

Barrachina, Teresa
Uncertainty and Sensitivity Analysis in the Neutronic Parameters Generation over the Coupled Thermalhydraulic-Neutronic Nuclear Power Plant Simulations  

Barrault, Maxime
A Non Overlapping Parallel Domain Decomposition Method Applied to the Simplified Transport Equations  

Barros, Ricardo C.
Analytical Reconstruction Schemes for Coarse-Mesh Spectral Nodal Solution of Slab-Geometry Sn Transport Problems  

Barry, D.P.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Barry, Devin
Benchmark Experiment of Neutron Resonance Scattering Models in Monte Carlo Codes  

Barry,Devin
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Baudron, Anne-Marie
Fuel Loading Pattern for Heterogeneous EPR Core Configuration Using a Distributed Evolutionary Algorithm  

Becker, B.
Rate of Convergence of Antithetic Transforms in Monte Carlo Simulation  

Becker, Bjorn
An Alternative Stochastic Doppler Broadening Algorithm  

Becker, Maarten
Energy-Angle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion  

Becker, Maarten
Time-Dependent Anisotropic Distributed Source Capability in Transient 3-D Transport Code TORT-TD  

Becker, Troy L.
The Application of Weight Windows to “Global” Monte Carlo Problems  

Bednarz, Bryan
Applications of Monte Carlo Computational Framework of a Medical Accelerator Used for Radiation Treatment  

Begalli, Marcia
Object Oriented Design of Anthropomorphic Phantoms and GEANT4-Based Implementations  

Begalli, Marcia
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Bekar, Kursat
A Case Study to Test MOZAIK for Different Optimization Problems  

Bekar, Kursat
Revisiting the TORT Solutions to the NEA Suite of Benchmarks for 3D Transport Methods and Codes over a Range in Parameter Space  

Belchior, Ana Lúcia
Air Kerma Distribution in an Irradiation Facility - Comparison of Monte Carlo Simulations with Physical Dosimetry Measurements  

Benstead, James
A New Approach to the Use of Group Scattering Data in Monte Carlo Neutron Transport  

Benzi, Michele
Negative Flux Fixups in Discontinuous Finite Element SN Transport  

Bernard, Franck
Application of Advanced Self-Shielding Models to Criticality-Safety Studies  

Bernnat, Wolfgang
Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations  

Bernnat, Wolfgang
Analyses of High Temperature Pebble Bed Reactors with Plutonium Fuel  

Berry, Ray A.
A Simple and Efficient Diffuse Interface Method for Compressible Two-Phase Flows  

Bess, John Darrell
Preliminary Benchmark Evaluation of Japan’s High Temperature Engineering Test Reactor  

Bhat, Ishwara
Optimization of a Novel Solid-State Self Powered Neutron Detector  

Bidaud, Adrien
Nuclear Data Uncertainty Analysis Using the Coupling of DRAGON with SUSD3D  

Bird, Adam J.
Testing of the Tetrahedral Mesh Import Capability for Importing Converted CAD Files for Shielding and Criticality Calculations with MONK and MCBEND  

Biryulina, Marina
Modeling of Radiation Transport in Coupled Atmosphere-Snow-Ice-Ocean Systems  

Bitteker, Leo J.
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Blakeman, Ed D
Forward-Weighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities  

Block, R.C.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Block, Robert C.
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Bohnhoff, Bill
Parallel Discrete Ordinates Methods in the SCEPTRE Project  

Bohnhoff, Bill
Software Engineering in the SCEPTRE Code  

Bokov, Pavel M.
An Automated Cross Section Parameterization Method for MTR Application  

Bolch, W.
Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications  

Bolch, Wesley E.
Application of Electron Dose Kernels to Account for Heterogeneities in Voxelized Phantoms  

Booth, Thomas E.
Improved Criticality Convergence via a Modified Monte Carlo Power Iteration Method  

Booth, Thomas E.
A Weighted Adjoint Source for Weight-Window Generation by Means of a Linear Tally Combination  

Bortot, Sara
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: Application to a Generation IV Lead Fast Reactor (LFR)  

Bosko, Andre
Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries  

Botes, Danniell
An Automated Cross Section Parameterization Method for MTR Application  

Bouriquet, Bertrand
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Bourne, Mark M.
Optimization of a Compton Suppression Detector System Using CdZnTe and Liquid Scintillators  

Boyarinov, Victor F.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Boyarinov, Victor F.
Realization of 3D Equations of Surface Harmonics Method in SUHAM-3D Code  

Boyd, William
The WhiteStar Development Project: Westinghouse’s Next Generation Core Design Simulator and Core Monitoring Software to Power the Nuclear Renaissance  

Brantley, Patrick S.
Levermore-Pomraning Model Results for an Interior Source Binary Stochastic Medium Benchmark Problem  

Brantley, Patrick S.
A Comparison of Monte Carlo Particle Transport Algorithms for Binary Stochastic Mixtures  

Brenizer Jr., Jack
A Case Study to Test MOZAIK for Different Optimization Problems  

Broeders, Cornelis
Energy-Angle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion  

Bromley, Blair P.
Comparison of MCNP and WIMS-AECL/RFSP Calculations against Critical Heavy Water Experiments in ZED-2 with CANFLEX-LVRF and CANFLEX-LEU Fuels  

Bronson, Frazier L.
Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries  

Brown, Forrest B.
Instructive Concepts about the Monte Carlo Fission Source Distribution  

Brown, Forrest B.
An Information Theory Based Analysis of Fission Source Correlation in Monte Carlo k-Eigenvalue Calculations  

Brown, Forrest B.
A Review of Monte Carlo Criticality Calculations - Convergence, Bias, Statistics  

Brown, Forrest B.
On-the-Fly Doppler Broadening for Monte Carlo Codes  

Bruna, G.
Implementation of a Plate-Type Fuel Model to a Multi-Physics Code and Benchmark Modeling of Special Power Excursion Reactor Tests  

Bruna, Giovanni
A 1st Order Formulation of a Reaction Rate Variation for Spatial and Energy Collapsing  

Buchan, Andrew
A Non-Linear Optimal Discontinuous Petrov-Galerkin Method for Stabilising the Solution of the Transport Equation  

Burns, Kimberly
Multi-Group Transport Methods for High-Resolution Neutron Activation Analysis  

Cahalan, Robert F.
Modeling and Analysis of Offbeam Lidar Returns from Thick Clouds, Snow, and Sea Ice  

Cairns, Brian
Inversion of Multi-Angle Radiation Measurements  

Caracappa, Peter
A Project to Design a Software Package for Reporting Multidetector CT (MDCT) Doses  

Caracappa, Peter
Multidetector CT (MDCT) Modeling for Organ Dose Assessments of Various Patient Phantoms  

Cardoso, João
Air Kerma Distribution in an Irradiation Facility - Comparison of Monte Carlo Simulations with Physical Dosimetry Measurements  

Carlson, Barbara
Inversion of Multi-Angle Radiation Measurements  

Caro, Edmund
Computation of Improved Compton Scattering Momentum Transfer  

Carpenter, David C.
A Comparison of Constant Power Depletion Algorithms  

Cartier, Julien
Computing Sensitivity and Handling Data Uncertainties in Activation Problems  

Cecil Lubitz
Comparison of Some Monte Carlo Models for Bound Hydrogen Scattering  

Chai, Xiaoming
The Linear Source Approximation in Three Dimension Characteristics Method  

Chambon, Richard Pierre
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Chang, Jae H.
A Piecewise Linear Discontinuous Finite Element Spatial Discretization of the Transport Equation in 2D Cylindrical Geometry  

Chauliac, Christian
Dr. Christian Chauliac (CEA - France) NURESIM: A European Software Platform for Nuclear Reactor Simulation  

Cheatham, Jesse
Radiative Transfer with Monte Carlo Predictor-Corrector Methods  

Cho, Nam Zin
Extension of Generating Non-Negative Scattering Cross-Sections for Two Dimensional Geometry  

Cho, Nam Zin
Monte Carlo Anchoring Method for Loosely-Coupled k-Eigenvalue Problem  

Christoforou, Stavros
Using a Zero-Variance Scheme to Accelerate the Fission Source Convergence in a Monte Carlo Calculation  

Chunyaev, Evgeniy
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Clarke, Shaun D.
Monte Carlo Simulation of the Full Multiplicity Distributions Measured with a Passive Counter  

Clarke, Shaun D.
Optimization of a Compton Suppression Detector System Using CdZnTe and Liquid Scintillators  

Clemente, Roberto
High Order Method of Characteristic for 2-D Unstructured Meshes  

Clifford, Ivor David
The Application of a Multi-Physics Toolkit to Spatial Reactor Dynamics  

Colmont, Didier A.
Improved Thermal Modeling of a SNF Shipping-Cask Drying  

Conlin, Jeremy L.
Relaxation Scheme for Monte Carlo Explicitly Restarted Arnoldi’s Method for Criticality Calculations  

Cooper, Andrew
Importing CAD Models into MONK and MCBEND  

Cooper, Andy
Testing of the Tetrahedral Mesh Import Capability for Importing Converted CAD Files for Shielding and Criticality Calculations with MONK and MCBEND  

Copestake, Alan Peter
A Consistent Diffusion Synthetic Acceleration Technique Utilising Discontinuity Factors  

Courau, Tanguy
PWR Assembly Transport Calculation: a Validation Benchmark Using DRAGON, PENTRAN, and MCNP  

Courau, Tanguy
Automatically Tuned Adaptive Differencing Algorithm for 3-D Sn Implemented in PENTRAN  

Couture, Aaron J.
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Cowan, Pat
Importing CAD Models into MONK and MCBEND  

Crawford, Martin J.
A Weight-Window Generator for Electron-Photon Transport in the Integrated TIGER Series Codes  

da Cruz, D. F.
Monte-Carlo-Based Simulation of LWR Cores with Innovative Fuel Concepts  

Dagan, R.
Rate of Convergence of Antithetic Transforms in Monte Carlo Simulation  

Dagan, Ron
An Alternative Stochastic Doppler Broadening Algorithm  

Dagan, Ron
Time-Dependent Anisotropic Distributed Source Capability in Transient 3-D Transport Code TORT-TD  

Dagan, Ron
Energy-Angle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion  

Dagan, Ron
Benchmark Experiment of Neutron Resonance Scattering Models in Monte Carlo Codes  

Dall'Osso, Aldo
Improvements and Core Applications of the Migration Mode Method  

Damian, Frederic
Neutronic Modeling for Pebble Bed Reactors  

Danon, Yaron
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Danon, Yaron
Optimization of a Novel Solid-State Self Powered Neutron Detector  

Danon,Y.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Danon,Yaron
Benchmark Experiment of Neutron Resonance Scattering Models in Monte Carlo Codes  

D'Auria, F.
The University of Pisa Calculations for the Phase I of the OECD/NEA UAM Benchmark  

D'Auria, Francesco
Prediction of Void Fraction Uncertainty Bands in BWR Fuel Bundles Using the CIAU Methodology  

D'Auria, Francesco
ATUCHA-2 PHWR Monte Carlo MCNP5 and KENO-VI Models Development and Application  

Davidson, Gregory G.
Sweepless Time-Dependent Transport Calculations Using the Staggered Block Jacobi Method  

Davis, Anthony B.
Radiation Transport Through Random Media Represented as Measurable Functions: Positive Versus Negative Spatial Correlations  

de Oliveira, Cassiano
Analysis and Numerical Solution for Multi-Physics Coupling of Neutron Diffusion and Thermomechanics in Spherical Fast Burst Reactors  

de Queiroz Filho, Pedro Pacheco
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

de Souza e Silva, Rosana
Object Oriented Design of Anthropomorphic Phantoms and GEANT4-Based Implementations  

de Souza Santos, Denison
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

de Souza-Santos, Denison
Object Oriented Design of Anthropomorphic Phantoms and GEANT4-Based Implementations  

Degweker, Shashikant
Extension of the Invariant Embedding Method for the Calculation of Particle Fluctuations  

DeHart, Mark David
Development of Generalized Perturbation Theory Capability within the SCALE Code Package  

Densmore, Jeffery D.
Time-Step Limits for a Monte Carlo Compton-Scattering Method  

Densmore, Jeffery D.
Asymptotic Analysis of Spatial Discretizations in Implicit Monte Carlo  

Detwiler, Rebecca
Assessment of Mark I Rod Irradiations in the UF Subcritical Water Tank Experiment Using Transport Methods  

Devlin, Matthew
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Ding, Aiping
A Project to Design a Software Package for Reporting Multidetector CT (MDCT) Doses  

Ding, Aiping
Deformable and Posture-Changeable Computational Phantoms and Dosimetry Data for Standard External-Beam Irradiations  

Dingley, Justin
Optimization of a Novel Solid-State Self Powered Neutron Detector  

Dion,Maxime
Comparison of Probabilistic and Deterministic Error Propagation Calculations in DRAGON  

Diop, Cheikh
Unbiased Minimum Variance Estimator of a Matrix Exponential Function. Application to Boltzmann/Bateman Coupled Equations Solving.  

Djalandinov, Alexander
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Do, Jean-Michel
Fuel Loading Pattern for Heterogeneous EPR Core Configuration Using a Distributed Evolutionary Algorithm  

Douglass, Steven J.
2-Dimensional PWR and BWR Whole Core Benchmark Problems  

Drindack, N.J.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Drumm, Clif
Parallel Discrete Ordinates Methods in the SCEPTRE Project  

Drumm, Clif
Software Engineering in the SCEPTRE Code  

Drumm, Clif
Order-Convergence Anomalies in Second-Order Finite Elements Transport Methods  

Dubinin, Anatoly A.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Dulla, Sandra
Subcriticality Determination by Neural-Based Inversion of Space-Energy Neutron Kinetic Equations  

Dulla, Sandra
Variational Methods in the Kinetic Modeling of Nuclear Reactors: Recent Advances  

Dumonteil, Eric
Unbiased Minimum Variance Estimator of a Matrix Exponential Function. Application to Boltzmann/Bateman Coupled Equations Solving.  

Durkee, Joe W. Jr.
MCNPX Graphics and Arithmetic Tally Upgrades  

Dutheillet, Yves
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Dweiri, Yousif
Comparison of MCNP and WIMS-AECL/RFSP Calculations against Critical Heavy Water Experiments in ZED-2 with CANFLEX-LVRF and CANFLEX-LEU Fuels  

Eaton, M
A Non-Linear Optimal Discontinuous Petrov-Galerkin Method for Stabilising the Solution of the Transport Equation  

Enqvist, Andreas
Combined Use of Neutron and Gamma Multiplicities for Determining Sample Parameters  

Epiney, Aaron
A New Cross-Section Generation Model in the Fast Code System and its Application to the Gen-IV Gas-Cooled Fast Reactor  

Erhard, Patrick
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Erradi, Lahoussine
Temperature Coefficient for PWR UO2 and MOX Lattices, Using 3D Transport Calculations and JEFF3.1.1 Library  

Espel, Federico Puente
High Accuracy Modeling for Advanced Nuclear Reactor Core Designs Using Monte Carlo Based Coupled Calculations  

Espel, Federico Puente
Application of Global Sensitivity Analysis Approach to Exercise I-1 of the OECD LWR UAM Benchmark  

Evans, Thomas M.
A Monte Carlo Synthetic Acceleration Method for the Non-Linear, Time-Dependent Diffusion Equation  

Evans, Thomas M.
Automated Weight-Window Generation for Threat Detection Applications Using ADVANTG  

Falgout, Robert D.
Analysis of Massively Parallel Discrete-Ordinates Transport Sweep Algorithms with Collisions  

Fan, Wesley
Parallel Discrete Ordinates Methods in the SCEPTRE Project  

Fan, Wesley
Software Engineering in the SCEPTRE Code  

Fanning, Thomas H.
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Fanning, Thomas H.
Multi-Resolution Modeling of Subassembly Pin Bundles for Advanced Fast Reactor Safety Simulations  

Fatone, Massimo
Spatial Meshing Effect and Reflector Treatment in PWR Core Modeling  

Faure, F.
Importing CAD to TRIPOLI(R)  

Favorite, Jeffrey A.
Variational Reactivity Estimates: New Analyses and New Results  

Fehri, Majid Fassi
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Fernex, Frederic
Application of Advanced Self-Shielding Models to Criticality-Safety Studies  

Ferrer, Rodolfo
A Robust Arbitrarily High Order Transport Method of the Characteristic Type for Unstructured Tetrahedral Grids  

Fichtl, Erin D.
Stochastic Methods for Uncertainty Quantification in Radiation Transport  

Filho, Hermes Alves
Analytical Reconstruction Schemes for Coarse-Mesh Spectral Nodal Solution of Slab-Geometry Sn Transport Problems  

Fischer, Paul F.
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Fischer, Ulrich
Use of McCad for the Generation of MCNP Models in Fusion Neutronics  

Flaska, Marek
Analytical Description of Pulses Measured with an Organic Liquid Scintillator for Pulse Shape Discrimination  

Flaska, Marek
Calibration of the BC-523A Capture-Gated Liquid Scintillation Detector  

Flaska, Marek
Monte Carlo Simulation of the Full Multiplicity Distributions Measured with a Passive Counter  

Fleurot, Fabrice
Importing CAD Models into MONK and MCBEND  

Fomichenko, Petr A.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Forget, Benoit
2-Dimensional PWR and BWR Whole Core Benchmark Problems  

Forslund Guimaraes, Petri
Parameterization of Two-Group Nodal Cross Section Data for POLCA-T BWR Transient Applications  

Forslund Guimaraes, Petri
Development of New Pin Power Recovery Methodology  

Fotiades, Nikolaos
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Fougeras, Philippe
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Fournier, Damien
Adaptive Algorithms for a Self-Shielding Wavelet-Based Galerkin Method  

Fournier, Damien
High-Order Discrete Ordinate Transport in Non-Conforming 2D Cartesian Meshes  

Fournier, Y.
Improvements of a Finite Volume Based Multigrid Method Applied to Elliptic Problems  

Franceschini, Fausto
Development of New Pin Power Recovery Methodology  

Franceschini, Fausto
Two-Dimensional Whole Core Transport Calculations Using PARAGON  

Franke, Brian C.
An hp-Adaptivity Approach for Monte Carlo Tallies  

Franke, Brian C.
A Weight-Window Generator for Electron-Photon Transport in the Integrated TIGER Series Codes  

Fujita, Yusaku
Hybrid Method of MOC and Sn Nodal for PWR Core Analysis  

Furfaro, Roberto
Subcriticality Determination by Neural-Based Inversion of Space-Energy Neutron Kinetic Equations  

Gabrielli, F.
Implementation of a Plate-Type Fuel Model to a Multi-Physics Code and Benchmark Modeling of Special Power Excursion Reactor Tests  

Gabrielli, Fabrizio
Assessment of ERANOS for HPLWR Core Analyses  

Ganapol, Barry D.
The Converged Sn Algorithm for Nuclear Criticality  

Ganapol, Barry Douglas
Subcriticality Determination by Neural-Based Inversion of Space-Energy Neutron Kinetic Equations  

Ganapol, Barry Douglas
Dose Verification for Accelerated Partial Breast Irradiation  

Ganapol, Barry Douglas
An Ultra-Fine Group Slowing Down Benchmark  

Garcia-Herranz, N.
Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry  

Gargioni, Elisabetta
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Garin, Vladimir P.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Gastaldo, Laura
High-Order Discrete Ordinate Transport in Non-Conforming 2D Cartesian Meshes  

Gaston, Derek
Framework for Simulation of Pellet/Cladding Thermal Interaction (PCTI) for Fuel Performance Calculations  

Gaston, Derek Ray
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Gaston, Derek Ray
MOOSE: A Parallel Computational Framework for Coupled Systems of Nonlinear Equations  

Gaston, Derek Ray
Computational Foundations for Reactor Fuel Performance Modeling  

Gavrona, Avigdor
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Gentile, Nick
Implicit Monte Carlo Radiation Transport in Multi-Physics Simulations  

Gesh, Christopher John
Multi-Group Transport Methods for High-Resolution Neutron Activation Analysis  

Ghazy, Rasha
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: Application to a Generation IV Lead Fast Reactor (LFR)  

Ghita, Gabriel
Design of a Neutron Detector Array for SNM Optimized by Radiation Transport Methods  

Ghita, Gabriel
Transport Methods Used for Homeland Security and Non-Proliferation Detection Applications: an Overview  

Ghita, Monica
Application of Electron Dose Kernels to Account for Heterogeneities in Voxelized Phantoms  

Ghita, Monica
Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications  

Ghrayeb, Shadi
Application of Global Sensitivity Analysis Approach to Exercise I-1 of the OECD LWR UAM Benchmark  

Ghrayeb, Shadi
Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels  

Gil, Choong-Sup
Benchmark Analysis of a Metallic Plutonium Fueled BFS-55-1 Critical Assembly  

Gill, Daniel Fury
A Jacobian-Free Newton-Krylov Iterative Scheme for Criticality Calculations Based on the Neutron Diffusion Equation  

Ginestar, Damian
Spectral Element Method for the Neutron Diffusion Equation on a Triangular Mesh  

Glushkov, Evgeniy S.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Goda, Joetta M.
Analysis of Godiva-IV Delayed-Critical and Super-Prompt-Critical Conditions  

Gohar, Yousry
MCNPX and MCB Coupled Methodology for the Burnup Calculation of the KIPT Accelerator Driven Subcritical System  

Gol'din, Vladimir Ya.
Multi-Level Methods for Solving Multigroup Transport Eigenvalue Problems in 1D Slab Geometry  

Golfier, Hervé
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Gonçalves, Isabel
Air Kerma Distribution in an Irradiation Facility - Comparison of Monte Carlo Simulations with Physical Dosimetry Measurements  

Gougar, Hans D.
A Comparison of Pebble Mixing and Depletion Algorithms Used in Pebble-Bed Reactor Equilibrium Cycle Simulation  

Gratton, Serge
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Greenman, Gregory M.
Enhancements to the Combinatorial Geometry Particle Tracker in the Mercury Monte Carlo Transport Code: Embedded Meshed and Domain Decomposition  

Gregson, Michael W.
Time Dependent Non-Extinction Probability for Prompt Critical Systems  

Griesheimer, David P.
Analysis of Distances between Inclusions in Finite One-Dimensional Binary Stochastic Materials  

Griesheimer, David P.
Rejection Sampling from a Spherical Harmonics Angular Flux Functional Expansion for a Discrete Ordinates to Monte Carlo Splice  

Grimod, Maurice
Neutronic Modeling for Pebble Bed Reactors  

Grosse, Dennis
Use of McCad for the Generation of MCNP Models in Fusion Neutronics  

Grosse, Dennis
Current Status of the CAD Interface Program McCad for MC Particle Transport Codes  

Grosswendt, Bernd
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Grove, Robert E.
Discrete Ordinate Mapping Algorithm for Region-Based Quadrature Sets  

Grove, Robert E.
Surface Mesh Refinement with the Slice Balance Approach (SBA)  

Grove, Robert E.
Effective Software Design for a Deterministic Transport System  

Gu, Jianwei
Multidetector CT (MDCT) Modeling for Organ Dose Assessments of Various Patient Phantoms  

Gu, Jianwei
A Project to Design a Software Package for Reporting Multidetector CT (MDCT) Doses  

Gubernatis, James E
Improved Criticality Convergence via a Modified Monte Carlo Power Iteration Method  

Gueorguiev, Andrey
Optimization of a Compton Suppression Detector System Using CdZnTe and Liquid Scintillators  

Guérin, Caroline
Improved Thermal Modeling of a SNF Shipping-Cask Drying  

Gukov, Sergei V.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Gurevich, Michael I.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Gurevich, Michael I.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

H. M. Broeders, Cornelis
An Alternative Stochastic Doppler Broadening Algorithm  

Hackel, Brian M.
FZ2NC: A Tool for Monte Carlo Transport Code Geometry Manipulation  

Hadad, K.
The Converged Sn Algorithm for Nuclear Criticality  

Hadad, Kamal
Dose Verification for Accelerated Partial Breast Irradiation  

Hadek, Jan
Validation of DYN3D Pin-Power Calculation against Experimental VVER-Full-Core Benchmark  

Haghighat, Alireza
Analysis and Benchmarking of PENTRAN Code using the OECD-NEA Benchmark Problems  

Haghighat, Alireza
Hybrid Sn and Ray-Tracing with Fictitious Quadrature for Simulation of SPECT  

Haghighat, Alireza
Accuracy of TITAN Based on a New OECD-NEA Benchmark over a Range in Parameter Space  

Haghighat, Alireza
A Combined Diagnostic Approach for Monte Carlo Source Convergence Identification  

Haghighat, Alireza
Analysis of SPECT Imaging Simulation Using the TITAN Transport Code  

Haight, Robert
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Hamilton, R.
Dose Verification for Accelerated Partial Breast Irradiation  

Hamilton, Steven P.
Negative Flux Fixups in Discontinuous Finite Element SN Transport  

Hamre, Borge
Modeling of Radiation Transport in Coupled Atmosphere-Snow-Ice-Ocean Systems  

Han, Bin
Applications of Monte Carlo Computational Framework of a Medical Accelerator Used for Radiation Treatment  

Hansen, Glen
Framework for Simulation of Pellet/Cladding Thermal Interaction (PCTI) for Fuel Performance Calculations  

Hansen, Glen
MOOSE: A Parallel Computational Framework for Coupled Systems of Nonlinear Equations  

Hansen, Glen
Computational Foundations for Reactor Fuel Performance Modeling  

Hauck, Cory D.
Filtered Spherical Harmonics Methods for Transport Problems  

Have, P.
Domain Decomposition Parallelization of Neutron Transport Calculations  

Hawari, Ayman I.
Evaluating the Graphite Thermal Neutron Scattering Law Using Molecular Dynamic Correlation Functions  

Hazama, Taira
Broad Group Cross Section Library for Fast Reactor Using Nuclide Dependent Collision Density  

He, Tao
Simulating Small Changes in System Response by MCNP5  

Hebert, Alain
Application of Advanced Self-Shielding Models to Criticality-Safety Studies  

Hebert, Alain
Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+  

Hebert, Alain
An Investigation of the Temperature Correlation Effect in Lattice Calculations  

Hehr, Brian Douglas
Evaluating the Graphite Thermal Neutron Scattering Law Using Molecular Dynamic Correlation Functions  

Henderson, Douglass L.
Adjoint Current-Based Approaches to Prostate Brachytherapy Optimization  

Henderson, Douglass L.
Acceleration Techniques for Direct Use of CAD-Based Geometries in Monte Carlo Radiation Transport  

Herrero, José-Javier
Performance of Whole Core Pin-by-Pin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations  

Hesse, Ulrich
DORTOREST: A Coupled Transport-Depletion Code System for LWR Fuel Assembly Burnup Calculations  

Hill, Tony
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Hino, Tetsushi
Development of Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix  

Hiruta, Hikaru
Analysis of an Earthquake-Initiated-Transient in a PBR  

Holloway, James P.
Multi-Grid Genetic Algorithms for Space Shield Design  

Holloway, James P.
A Quasi-Static Closure for 3rd Order Spherical Harmonics Time-Dependent Radiation Transport in 2-D  

Holloway, James P.
Relaxation Scheme for Monte Carlo Explicitly Restarted Arnoldi’s Method for Criticality Calculations  

Holloway, James Paul
Radiative Transfer with Monte Carlo Predictor-Corrector Methods  

Hoogenboom, J. Eduard
A Proposal for a Benchmark to Monitor the Performance of Detailed Monte Carlo Calculation of Power Densities in a Full Size Reactor Core  

Hoogenboom, J. Eduard
Using a Zero-Variance Scheme to Accelerate the Fission Source Convergence in a Monte Carlo Calculation  

Hoole, J.G.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Hoole, Jeff
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Hossain, Kamal
Analyses of High Temperature Pebble Bed Reactors with Plutonium Fuel  

Huang, Kai
Modified Nodal Integral Method Incorporated with Irregular-Shape Elements for Navier-Stokes Equations  

Hugot, Francois-Xavier
TRIPOLI4 Solutions of VVER-1000 Assembly and Core Benchmarks  

Hugot, Francois-Xavier
Use of TRIPOLI-4.5 Mesh Tally to Investigate Power Maps of the LEU-COMP-THERM-008 PWR Critical Lattices  

Hulsemann, F.
Improvements of a Finite Volume Based Multigrid Method Applied to Elliptic Problems  

Humbert, Philippe P.
Fast Gamma Ray Leakage Spectra Simulation  

Hykes, Joshua M.
Verification and Validation of Deterministic Radiation Transport Numerical Methods, Codes, and Nuclear Data for Estimating Radiation Dose to Patients During CT Scan  

Ishii, Kazuya
Development of Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix  

Ivanov, Kostadin
Uncertainty Analysis of COBRA-TF Void Distribution Predictions for the OECD/NRC BFBT Benchmark  

Ivanov, Kostadin
Application of Global Sensitivity Analysis Approach to Exercise I-1 of the OECD LWR UAM Benchmark  

Ivanov, Kostadin
Overview and Discussion of Phase I of the OECD LWR UAM Benchmark Activity  

Ivanov, Kostadin
Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels  

Ivanov, Kostadin
Verification & Validation and Uncertainty Analysis in Multi-Physics Modeling for Nuclear Reactor Design and Safety  

Ivanov, Kostadin
High Accuracy Modeling for Advanced Nuclear Reactor Core Designs Using Monte Carlo Based Coupled Calculations  

Iwasaki, Tomohiko
Development of Open Code System for BWR Lattice Calculation by Monte Carlo Method  

James, Michael R.
MCNPX Graphics and Arithmetic Tally Upgrades  

Jansen, Jan T.M.
Development of PC Based Monte Carlo Simulations for the Calculation of Scanner-Specific Normalized Organ Doses from CT  

Jarrell, Joshua
Discrete Ordinate Mapping Algorithm for Region-Based Quadrature Sets  

Jasak, Hrvoje
The Application of a Multi-Physics Toolkit to Spatial Reactor Dynamics  

Jessee, Matthew L.
Development of Generalized Perturbation Theory Capability within the SCALE Code Package  

Jimenez Escalante, Javier
Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry  

Jiménez, Javier
Performance of Whole Core Pin-by-Pin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations  

Jing, Wenjia
Radiation Transport through Random Media  

Joo, Han Gyu
Monte Carlo Depletion and Uncertainty Analysis for a TRU Fuel Assembly Using JENDL3.3 Covariance Data  

Joo, Han Gyu
Decoupled Planar MOC Solution for Dynamic Group Constant Generation in Direct Three-Dimensional Core Calculations  

Joo, Han Gyu
Investigation of Multigroup Effect in Transient Calculation to Determine Hottest Pin Enthalpy  

Joo, Hyung-Kook
Breakeven Core Design Studies for a Sodium Cooled Fast Reactor  

Joubert, Wessel
An Automated Cross Section Parameterization Method for MTR Application  

Joubert, Wessel
A Comparison of Pebble Mixing and Depletion Algorithms Used in Pebble-Bed Reactor Equilibrium Cycle Simulation  

Joy, Kenneth
Mercury + VisIt: Integration of a Real-Time Graphical Analysis Capability into a Monte Carlo Transport Code  

Joy, Kenneth
Enhancements to the Combinatorial Geometry Particle Tracker in the Mercury Monte Carlo Transport Code: Embedded Meshed and Domain Decomposition  

Juanas, Jesús
Uncertainty and Sensitivity Analysis in the Neutronic Parameters Generation over the Coupled Thermalhydraulic-Neutronic Nuclear Power Plant Simulations  

Jung, Yeon Sang
Decoupled Planar MOC Solution for Dynamic Group Constant Generation in Direct Three-Dimensional Core Calculations  

Kadioglu, Samet Y.
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Kadioglu, Samet Y.
Analysis and Numerical Solution for Multi-Physics Coupling of Neutron Diffusion and Thermomechanics in Spherical Fast Burst Reactors  

Kamerow,Sofia
Overview and Discussion of Phase I of the OECD LWR UAM Benchmark Activity  

Kane, Steven
Study of the Prompt Gamma Ray Signal from Fissions in Special Nuclear Materials Induced Using an Associated Particle Neutron Generator  

Karino, Tatsuya
Development of Open Code System for BWR Lattice Calculation by Monte Carlo Method  

Karthikeyan, Ramamoorthy
Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+  

Kassianov, Evgueni
Markovian Approach: from Ising Model to Stochastic Radiative Transfer  

Kaushik, Dinesh
Recent Research Progress on UNIC at Argonne National Laboratory  

Kaushik, Dinesh
Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics  

Keith, Rodney L.
Order-of-Convergence Study of a Condensed-History Algorithm Implementation  

Keller, Katherine
Analysis of SPECT Imaging Simulation Using the TITAN Transport Code  

Kelley, Timothy
Fourier Analysis of Cell-Wise Block-Jacobi Splitting in Two-Dimensional Geometry  

Kelsey, Charles T. IV
Multigroup Neutron Dose Calculations for Proton Therapy  

Kensek, Ronald P.
A Weight-Window Generator for Electron-Photon Transport in the Integrated TIGER Series Codes  

Kensek, Ronald P.
An hp-Adaptivity Approach for Monte Carlo Tallies  

Kensek, Ronald P.
Order-of-Convergence Study of a Condensed-History Algorithm Implementation  

Kiedrowski, Brian C.
An Information Theory Based Analysis of Fission Source Correlation in Monte Carlo k-Eigenvalue Calculations  

Kim, Chan Hyeong
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Kim, Chang Hyo
Monte Carlo Depletion and Uncertainty Analysis for a TRU Fuel Assembly Using JENDL3.3 Covariance Data  

Kim, Chang Hyo
Application of Inactive Cycle Stopping Criteria for Monte Carlo Wielandt Calculations  

Kim, Do Heon
Benchmark Analysis of a Metallic Plutonium Fueled BFS-55-1 Critical Assembly  

Kim, Jae Hak
Investigation of Multigroup Effect in Transient Calculation to Determine Hottest Pin Enthalpy  

Kim, Jong Woon
Extension of Generating Non-Negative Scattering Cross-Sections for Two Dimensional Geometry  

Kim, Sang-Ji
Benchmark Analysis of a Metallic Plutonium Fueled BFS-55-1 Critical Assembly  

Kim, Yeong-Il
Breakeven Core Design Studies for a Sodium Cooled Fast Reactor  

King, Steven H.
Verification and Validation of Deterministic Radiation Transport Numerical Methods, Codes, and Nuclear Data for Estimating Radiation Dose to Patients During CT Scan  

Kirschenmann, Wilfried
Massively Parallel Solving of 3D Simplified Pn Equations on Graphics Processing Units  

Kitada, Takanori
Hybrid Method of MOC and Sn Nodal for PWR Core Analysis  

Kliem, Soeren
Influence of the Neutron-Kinetic Feedback Parameter Variation on an Anticipated Transient without Scram in a PWR  

Klingensmith, Jesse J.
Verification and Validation of Deterministic Radiation Transport Numerical Methods, Codes, and Nuclear Data for Estimating Radiation Dose to Patients During CT Scan  

Knobelspiesse, Kirk
Inversion of Multi-Angle Radiation Measurements  

Knoll, Dana
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Knoll, Dana
Analysis and Numerical Solution for Multi-Physics Coupling of Neutron Diffusion and Thermomechanics in Spherical Fast Burst Reactors  

Knoll, Dana
Application of the Jacobian-Free Newton-Krylov Method in Computational Reactor Physics  

Knyazikhin, Yuri
Canopy Spectral Invariants: A New Concept in Remote Sensing of Vegetation  

Kobayashi, Keisuke
Radiation Transport Benchmarks For Simple Geometries With Void Regions Using The Spherical Harmonics Method  

Kodeli, Ivo
Overview and Discussion of Phase I of the OECD LWR UAM Benchmark Activity  

Kolev, Nikola
TRIPOLI4 Solutions of VVER-1000 Assembly and Core Benchmarks  

Koltick, David S.
Study of the Prompt Gamma Ray Signal from Fissions in Special Nuclear Materials Induced Using an Associated Particle Neutron Generator  

Kompaniets, Georgiy V.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Kovtonyuk, Andriy
Prediction of Void Fraction Uncertainty Bands in BWR Fuel Bundles Using the CIAU Methodology  

Kraftcheck, Jason A.
Acceleration Techniques for Direct Use of CAD-Based Geometries in Monte Carlo Radiation Transport  

Kraftcheck, Jason A.
A Weight-Window Generator for Electron-Photon Transport in the Integrated TIGER Series Codes  

Kryuchkov, Vyacheslav P.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Krzykacz-Hausmann, Bernard
Uncertainty Analysis of COBRA-TF Void Distribution Predictions for the OECD/NRC BFBT Benchmark  

Kucukboyaci, Vefa N.
Two-Dimensional Whole Core Transport Calculations Using PARAGON  

Kulesza, Joel Aaron
Sensitivity Study to Optimize the Thickness of a Moderator for Use in the AP1000 Source, Intermediate, and Power Range Excore Detectors  

Lacis, Andrew
Inversion of Multi-Angle Radiation Measurements  

Langenbuch, Siegfried
Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations  

Langenbuch, Siegfried
Generation of Consistent Conservative Cross Section Data for the Coupled System Code ATHLET-QUABOX/CUBBOX  

Laptev, Alexander
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Larsen, Edward W.
A Hybrid Monte Carlo-S2 Method for Preserving Neutron Transport Effects  

Larsen, Edward W.
A Linear Stability Analysis for Nonlinear, 1-D, Gray Implicit Monte Carlo Calculations  

Larsen, Edward W.
A Time-Dependent Fleck Factor to Enhance the Accuracy of the Implicit Monte Carlo Equations  

Larsen, Edward W.
The Application of Weight Windows to “Global” Monte Carlo Problems  

Larsen, Edward W.
A Hybrid Monte Carlo-Deterministic Approach to Improve the Accuracy and Efficiency of Monte Carlo Calculations for Thermal Radiative Transfer  

Larsen, Edward W.
Sweepless Time-Dependent Transport Calculations Using the Staggered Block Jacobi Method  

Larsen, Edward W.
Anisotropic Diffusion in Model 2-D Pebble-Bed Reactor Cores  

Larsen, Edward W.
Application of the 'Functional Monte Carlo' Method to Estimate Continuous Energy k-Eigenvalues and Eigenfunctions  

Lathuiliere, Bruno
A Non Overlapping Parallel Domain Decomposition Method Applied to the Simplified Transport Equations  

Lautard, Jean-Jacques
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Lautard, Jean-Jacques
Fuel Loading Pattern for Heterogeneous EPR Core Configuration Using a Distributed Evolutionary Algorithm  

Le Tellier, Romain
High-Order Discrete Ordinate Transport in Non-Conforming 2D Cartesian Meshes  

Le Tellier, Romain
Adaptive Algorithms for a Self-Shielding Wavelet-Based Galerkin Method  

Le Texier, P.
Importing CAD to TRIPOLI(R)  

Lebrun-Grandie, Damien
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Lee, C.
Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications  

Lee, Ki-Bog
Breakeven Core Design Studies for a Sodium Cooled Fast Reactor  

Lee, Yi-Kang
Use of TRIPOLI-4.5 Mesh Tally to Investigate Power Maps of the LEU-COMP-THERM-008 PWR Critical Lattices  

Lee, Young-Ouk
Benchmark Analysis of a Metallic Plutonium Fueled BFS-55-1 Critical Assembly  

Lee,Young-Ouk
Extension of Generating Non-Negative Scattering Cross-Sections for Two Dimensional Geometry  

Leinweber, G.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Leinweber, Gregory
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Lenain, Richard
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Lengar, Igor
MCNP and Visualization of Neutron Flux and Power Distributions  

Leppänen, Jaakko
Burnup Calculation Capability in the PSG2/Serpent Monte Carlo Reactor Physics Code  

Leroyer, Hadrien
DRAGON Evaluation of the Effect of Heterogeneous Environment on PWR Assemblies  

Leung, Kenneth
Prediction of Void Fraction Uncertainty Bands in BWR Fuel Bundles Using the CIAU Methodology  

Levine, Samuel
Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels  

Lewis, Elmer
Professor Elmer Lewis (Northwestern University) Toward Whole-Core Neutron Transport Without Spatial Homogenization  

LiCausi, Nicholas
Optimization of a Novel Solid-State Self Powered Neutron Detector  

Liu, Emily
Benchmark Experiment of Neutron Resonance Scattering Models in Monte Carlo Codes  

Liu, Haikuan
A Project to Design a Software Package for Reporting Multidetector CT (MDCT) Doses  

Liu, Ping
Implementation of a Plate-Type Fuel Model to a Multi-Physics Code and Benchmark Modeling of Special Power Excursion Reactor Tests  

Loewen Jr., Eric
Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels  

Lohnert, G
Energy-Angle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion  

Lohnert, Guenter
An Alternative Stochastic Doppler Broadening Algorithm  

Lohnert, Günter
Analyses of High Temperature Pebble Bed Reactors with Plutonium Fuel  

Lowrie, Robert B.
Effects of the Temperature Discretization on Numerical Methods for Thermal Radiation Transport  

Lowrie, Robert B.
Filtered Spherical Harmonics Methods for Transport Problems  

Lowrie, Robert B.
Time-Step Limits for a Monte Carlo Compton-Scattering Method  

Lozano Montero, Juan Andres
Development and Performance of the ANDES/COBRA-III Coupled System in Hexagonal-Z Geometry  

Lu, Jian-Qiang
Optimization of a Novel Solid-State Self Powered Neutron Detector  

Lu, Lei
CAD-Based Modeling for 3-D Particle Transport  

Macian, Rafael
Uncertainty and Sensitivity Analysis in the Neutronic Parameters Generation over the Coupled Thermalhydraulic-Neutronic Nuclear Power Plant Simulations  

Magat, Philippe
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Maginot, Peter
A Positive Nonlinear Closure for the Sn Equations with Linear Discontinuous Spatial Differencing  

Mahadevan, Vijay
Verification of Multiphysics Software: Space and Time Convergence Studies for Nonlinearly Coupled Applications  

Maldonado, Ivan
An Ultra-Fine Group Slowing Down Benchmark  

Manalo, Kevin
Neutron Response of Silicon Carbide Semiconductor Detectors from Deterministic Adjoint Transport Calculations  

Manalo, Kevin
Automatically Tuned Adaptive Differencing Algorithm for 3-D Sn Implemented in PENTRAN  

Manturov, Gennady N.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Marleau, Guy
Nuclear Data Uncertainty Analysis Using the Coupling of DRAGON with SUSD3D  

Marleau, Guy
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Marleau, Guy
Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+  

Marleau, Guy
PWR Assembly Transport Calculation: a Validation Benchmark Using DRAGON, PENTRAN, and MCNP  

Marleau, Guy
DRAGON Evaluation of the Effect of Heterogeneous Environment on PWR Assemblies  

Marleau, Guy
Comparison of Probabilistic and Deterministic Error Propagation Calculations in DRAGON  

Martin, Julie
Testing of the Tetrahedral Mesh Import Capability for Importing Converted CAD Files for Shielding and Criticality Calculations with MONK and MCBEND  

Martin, Nicolas
Application of Advanced Self-Shielding Models to Criticality-Safety Studies  

Martin, William R.
On-the-Fly Doppler Broadening for Monte Carlo Codes  

Martin, William R.
Kernel Density Estimated Monte Carlo Global Flux Tallies  

Martin, William R.
A Proposal for a Benchmark to Monitor the Performance of Detailed Monte Carlo Calculation of Power Densities in a Full Size Reactor Core  

Martin, William R.
A Hybrid Monte Carlo-S2 Method for Preserving Neutron Transport Effects  

Martin, William R.
Radiative Transfer with Monte Carlo Predictor-Corrector Methods  

Martin, William R.
Noise Analysis of Smoothed Residual Acceleration, a Monte Carlo Neutron Source Convergence Algorithm  

Martineau, Richard
Framework for Simulation of Pellet/Cladding Thermal Interaction (PCTI) for Fuel Performance Calculations  

Martineau, Richard C.
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Martinolli, Emanuele
APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic Multi-Purpose Code for Core Physics Analysis  

Martins, Maximiano
Object Oriented Design of Anthropomorphic Phantoms and GEANT4-Based Implementations  

Maschek, Werner
Implementation of a Plate-Type Fuel Model to a Multi-Physics Code and Benchmark Modeling of Special Power Excursion Reactor Tests  

Maschek, Werner
Assessment of ERANOS for HPLWR Core Analyses  

Masiello, Emiliano
High Order Method of Characteristic for 2-D Unstructured Meshes  

Massart, Sebastien
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Matsumoto, Hideki
Hybrid Method of MOC and Sn Nodal for PWR Core Analysis  

Mattes, Margarete
Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations  

Mayhue, Larry
The WhiteStar Development Project: Westinghouse’s Next Generation Core Design Simulator and Core Monitoring Software to Power the Nuclear Renaissance  

Mazzantini, Oscar
ATUCHA-2 PHWR Monte Carlo MCNP5 and KENO-VI Models Development and Application  

McClarren, Ryan G.
Filtered Spherical Harmonics Methods for Transport Problems  

McClarren, Ryan G.
Effects of the Temperature Discretization on Numerical Methods for Thermal Radiation Transport  

Mechitoua , Boukhmes
Fast Gamma Ray Leakage Spectra Simulation  

Mechitoua, N.
Improvements of a Finite Volume Based Multigrid Method Applied to Elliptic Problems  

Meier, Astrid
Analyses of High Temperature Pebble Bed Reactors with Plutonium Fuel  

Memoli, Vito
Benchmarking of the SCALE Code Package and Multi-Group Cross Section Libraries for Analysis of Lead-Cooled Fast Reactor  

Menaa, Nabil
Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries  

Merk, B.
An Analytical Solution for an External Source Problem with Delayed Neutrons Using the Telegraphers Equation  

Merk, Bruno
On the Influence of Spatial Discretization in LWR Steady State and Burnup Calculations with HELIOS 1.9  

Merton, Simon R.
A Non-Linear Optimal Discontinuous Petrov-Galerkin Method for Stabilising the Solution of the Transport Equation  

Mihailescu, Liviu Cristian
Calibration of the BC-523A Capture-Gated Liquid Scintillation Detector  

Mikityuk, Konstantin
A New Cross-Section Generation Model in the Fast Code System and its Application to the Gen-IV Gas-Cooled Fast Reactor  

Mikus, Jan Martin
Axial Buckling Determination in a Reactor Core Containing Spacer Grid  

Milgram, Michael S.
Rate of Convergence of Antithetic Transforms in Monte Carlo Simulation  

Militão, Damiano da Silva
Analytical Reconstruction Schemes for Coarse-Mesh Spectral Nodal Solution of Slab-Geometry Sn Transport Problems  

Miller, Eric
Monte Carlo Simulation of the Full Multiplicity Distributions Measured with a Passive Counter  

Miller, Thomas M.
Automated Weight-Window Generation for Threat Detection Applications Using ADVANTG  

Millman, David L.
Analysis of Distances between Inclusions in Finite One-Dimensional Binary Stochastic Materials  

Mineev-Weinstein, Mark
Radiation Transport Through Random Media Represented as Measurable Functions: Positive Versus Negative Spatial Correlations  

Miró, Rafael
Qualification of the TH-3DNK Coupled Code RELAP5/PARCSv2.7 Against a BWR Unstable Point at Peach Bottom Nuclear Power Plant  

Miró, Rafael
Uncertainty and Sensitivity Analysis in the Neutronic Parameters Generation over the Coupled Thermalhydraulic-Neutronic Nuclear Power Plant Simulations  

Mishchenko, Michael
Transfer of Electromagnetic Energy in Particulate Media: from Wave Theory of Scattering to Ballistic Transport Equation  

Miss, Joachim
Application of Advanced Self-Shielding Models to Criticality-Safety Studies  

Mitsuyasu, Takeshi
Development of Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix  

Mittag, Siegfried
Influence of the Neutron-Kinetic Feedback Parameter Variation on an Anticipated Transient without Scram in a PWR  

Mittag, Siegfried
Validation of DYN3D Pin-Power Calculation against Experimental VVER-Full-Core Benchmark  

Monti, Lanfranco
Coupled ERANOS/TRACE System for HPLWR 3 Pass Core Analyses  

Monti, Lanfranco
Assessment of ERANOS for HPLWR Core Analyses  

Morel, Jim
A Positive Nonlinear Closure for the Sn Equations with Linear Discontinuous Spatial Differencing  

Morel, Jim
Galerkin-Quadratures for the Sn Method in 2D Cartesian Geometries and Application to Forward-Peaked Scattering Particle Transport Problems  

Morel, Jim E.
A Linear-Discontinuous Cut-Cell Discretization for the Sn Equations in R-Z Geometry  

Morgan, Dane
Determination of Solute-Interstitial Interactions in Ni-Cr by First Principles  

Mori, Masaaki
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Mosher, Scott W.
Automated Weight-Window Generation for Threat Detection Applications Using ADVANTG  

Mosher, Scott W.
A Monte Carlo Synthetic Acceleration Method for the Non-Linear, Time-Dependent Diffusion Equation  

Mosteller, Russell D.
Analysis of Godiva-IV Delayed-Critical and Super-Prompt-Critical Conditions  

Mousseau, Vincent
Modified Choke Flow Criterion for the Two-Phase Two-Fluid Model  

Mousseau, Vincent
Verification of Multiphysics Software: Space and Time Convergence Studies for Nonlinearly Coupled Applications  

Muller, Erwin
Development of New Pin Power Recovery Methodology  

Muller, Erwin Z.
An Extension of the Multigroup Analytic Nodal Method (MANM) to Problems in Hexagonal-Z Geometry  

Muller, Erwin
Parameterization of Two-Group Nodal Cross Section Data for POLCA-T BWR Transient Applications  

Mureithi, Njuki William
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Na, Yong Hum
Deformable and Posture-Changeable Computational Phantoms and Dosimetry Data for Standard External-Beam Irradiations  

Nabbi, Rahim
Monte-Carlo-Based Simulation of LWR Cores with Innovative Fuel Concepts  

Najafabadi, Reza
Determination of Solute-Interstitial Interactions in Ni-Cr by First Principles  

Nakazawa, Dante
Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries  

Nataf, F.
Domain Decomposition Parallelization of Neutron Transport Calculations  

Nease, Brian R.
Instructive Concepts about the Monte Carlo Fission Source Distribution  

Nease, Brian R.
The Appearance of Complex Values in Monte Carlo Calculation of Degenerate Eigenvalues  

Nelson, Ron O.
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Nevinitsa, Vladimir A.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Newman, Chris
Framework for Simulation of Pellet/Cladding Thermal Interaction (PCTI) for Fuel Performance Calculations  

Newman, Chris
Computational Foundations for Reactor Fuel Performance Modeling  

Newman, Christopher
MOOSE: A Parallel Computational Framework for Coupled Systems of Nonlinear Equations  

Nielsen, Dale E. Jr.
FZ2NC: A Tool for Monte Carlo Transport Code Geometry Manipulation  

Noblat, Etienne
Nuclear Data Uncertainty Analysis Using the Coupling of DRAGON with SUSD3D  

Novog, David R.
Prediction of Void Fraction Uncertainty Bands in BWR Fuel Bundles Using the CIAU Methodology  

O'Brien, Matthew
Enhancements to the Combinatorial Geometry Particle Tracker in the Mercury Monte Carlo Transport Code: Embedded Meshed and Domain Decomposition  

O'Brien, Matthew Joseph
Mercury + VisIt: Integration of a Real-Time Graphical Analysis Capability into a Monte Carlo Transport Code  

O'Donnell, John M.
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Oh, Kyeong S.
A Quasi-Static Closure for 3rd Order Spherical Harmonics Time-Dependent Radiation Transport in 2-D  

Ohoka, Yasunori
Study of the Acceleration of Nuclide Burnup Calculation Using GPU with CUDA  

Ohoka, Yasunori
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Okui, Shota
Study of the Acceleration of Nuclide Burnup Calculation Using GPU with CUDA  

Olekhnovitch, Andrei
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Oleynik, Dmitry S.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Oliveira, Francisco Bruno
Analytical Reconstruction Schemes for Coarse-Mesh Spectral Nodal Solution of Slab-Geometry Sn Transport Problems  

Ortensi, Javier
Improved Prediction of the Doppler Effect in TRISO Fuel  

Ortensi, Javier
Analysis of an Earthquake-Initiated-Transient in a PBR  

Osipov, S. L.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Ougouag, Abderrafi
Analysis of an Earthquake-Initiated-Transient in a PBR  

Ougouag, Abderrafi
A Hybrid Diffusion/Transport Method  

Ougouag, Abderrafi
Improved Prediction of the Doppler Effect in TRISO Fuel  

Ougouag, Abderrafi
A Simplified 2D HTTR Benchmark Problem  

Ouisloumen, Mohamed
Two-Dimensional Whole Core Transport Calculations Using PARAGON  

Pain, Chris
A Non-Linear Optimal Discontinuous Petrov-Galerkin Method for Stabilising the Solution of the Transport Equation  

Palmer, Todd S.
A Diffusion Synthetic Accelerated Linear Discontinuous Version of the Spherical Geometry Method of Tubes  

Palmer, Todd S.
Levermore-Pomraning Model Results for an Interior Source Binary Stochastic Medium Benchmark Problem  

Palmiotti, Giuseppe
Recent Research Progress on UNIC at Argonne National Laboratory  

Palmiotti, Giuseppe
Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics  

Pandya, Tara
Scalable Parallel Prefix Solvers for Discrete Ordinates Transport  

Pandya,Tara M.
Method of Long Characteristics Applied in Space and Time  

Parisi, C.
The University of Pisa Calculations for the Phase I of the OECD/NEA UAM Benchmark  

Parisi, Carlo
ATUCHA-2 PHWR Monte Carlo MCNP5 and KENO-VI Models Development and Application  

Park, Ho Jin
Monte Carlo Depletion and Uncertainty Analysis for a TRU Fuel Assembly Using JENDL3.3 Covariance Data  

Park, Ryosuke
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Park, Ryosuke
Application of the Jacobian-Free Newton-Krylov Method in Computational Reactor Physics  

Pautz, Andreas
DORTOREST: A Coupled Transport-Depletion Code System for LWR Fuel Assembly Burnup Calculations  

Pautz, Andreas
Uncertainty Analysis of COBRA-TF Void Distribution Predictions for the OECD/NRC BFBT Benchmark  

Pautz, Andreas
Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations  

Pautz, Andreas
Time-Dependent Anisotropic Distributed Source Capability in Transient 3-D Transport Code TORT-TD  

Pautz, Andreas
Energy-Angle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion  

Pautz, Shawn
Scalable Parallel Prefix Solvers for Discrete Ordinates Transport  

Pautz, Shawn
Parallel Discrete Ordinates Methods in the SCEPTRE Project  

Pautz, Shawn
Software Engineering in the SCEPTRE Code  

Pazsit, Imre
Combined Use of Neutron and Gamma Multiplicities for Determining Sample Parameters  

Pazsit, Imre
Extension of the Invariant Embedding Method for the Calculation of Particle Fluctuations  

Pecchia, Marco
ATUCHA-2 PHWR Monte Carlo MCNP5 and KENO-VI Models Development and Application  

Peerani, Paolo
Monte Carlo Modeling of Neutron Coincidence Counting Systems for Nuclear Safeguards  

Peerani, Paolo
Monte Carlo Simulation of the Full Multiplicity Distributions Measured with a Passive Counter  

Pelloni, Sandro
A New Cross-Section Generation Model in the Fast Code System and its Application to the Gen-IV Gas-Cooled Fast Reactor  

Peluso, Vincenzo
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: Application to a Generation IV Lead Fast Reactor (LFR)  

Pencer, Jeremy
Comparison of MCNP and WIMS-AECL/RFSP Calculations against Critical Heavy Water Experiments in ZED-2 with CANFLEX-LVRF and CANFLEX-LEU Fuels  

Penkrot, Vincent S.
The WhiteStar Development Project: Westinghouse’s Next Generation Core Design Simulator and Core Monitoring Software to Power the Nuclear Renaissance  

Peplow, Douglas E.
Criticality Accident Alarm System Modeling with SCALE  

Peplow, Douglas
Forward-Weighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities  

Perin, Yann
Uncertainty Analysis of COBRA-TF Void Distribution Predictions for the OECD/NRC BFBT Benchmark  

Petitpas, Fabien
A Simple and Efficient Diffuse Interface Method for Compressible Two-Phase Flows  

Petrie, Lester M. Jr.
Criticality Accident Alarm System Modeling with SCALE  

Petrov, Nikolay
TRIPOLI4 Solutions of VVER-1000 Assembly and Core Benchmarks  

Petrovic, Bojan
Benchmarking of the SCALE Code Package and Multi-Group Cross Section Libraries for Analysis of Lead-Cooled Fast Reactor  

Petruzzi, Alessandro
Prediction of Void Fraction Uncertainty Bands in BWR Fuel Bundles Using the CIAU Methodology  

Pia, Maria Grazia
Object Oriented Design of Anthropomorphic Phantoms and GEANT4-Based Implementations  

Pia, Maria Grazia
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Picca, Paolo
Subcriticality Determination by Neural-Based Inversion of Space-Energy Neutron Kinetic Equations  

Picca, Paolo
Variational Methods in the Kinetic Modeling of Nuclear Reactors: Recent Advances  

Pintor, Sebastian Gonzalez
Spectral Element Method for the Neutron Diffusion Equation on a Triangular Mesh  

Plagne, Laurent
Massively Parallel Solving of 3D Simplified Pn Equations on Graphics Processing Units  

Platt, Gustavo M.
Analytical Reconstruction Schemes for Coarse-Mesh Spectral Nodal Solution of Slab-Geometry Sn Transport Problems  

Ploix, Stéphane
Massively Parallel Solving of 3D Simplified Pn Equations on Graphics Processing Units  

Plower, Thomas
Assessment of Mark I Rod Irradiations in the UF Subcritical Water Tank Experiment Using Transport Methods  

Plower, Thomas
Neutron Response of Silicon Carbide Semiconductor Detectors from Deterministic Adjoint Transport Calculations  

Pointer, W. David
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Pointer, W. David
Multi-Resolution Modeling of Subassembly Pin Bundles for Advanced Fast Reactor Safety Simulations  

Polyakov, Dmitriy N.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Poncot, Angelique
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Ponçot, Angélique
Massively Parallel Solving of 3D Simplified Pn Equations on Graphics Processing Units  

Ponomarev, Aleksandr S.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Ponomarev-Stepnoi, Nikolay N.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Popescu, Ovidiu M.
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Popov, Alexi Ventzeslavov
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Popov, Alexi Ventzeslavov
Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+  

Pounders, Justin
A Simplified 2D HTTR Benchmark Problem  

Pozzi, Sara A.
Optimization of a Compton Suppression Detector System Using CdZnTe and Liquid Scintillators  

Pozzi, Sara A.
Monte Carlo Simulation of the Full Multiplicity Distributions Measured with a Passive Counter  

Pozzi, Sara A.
Calibration of the BC-523A Capture-Gated Liquid Scintillation Detector  

Pozzi, Sara A.
Analytical Description of Pulses Measured with an Organic Liquid Scintillator for Pulse Shape Discrimination  

Prinja, Anil K.
Stochastic Methods for Uncertainty Quantification in Radiation Transport  

Prinja, Anil K.
Time Dependent Non-Extinction Probability for Prompt Critical Systems  

Prinja, Anil K.
A Theoretical Result for Moment-Preserving Approximations to the Landau/Vavilov Straggling Model  

Prinja, Anil K.
An Analysis of Moment Preserving Methods for High Energy Ion Transport  

Prinja, Anil K.
Multigroup Neutron Dose Calculations for Proton Therapy  

Prinsloo, Rian H.
An Automated Cross Section Parameterization Method for MTR Application  

Procassini, Richard
Mercury + VisIt: Integration of a Real-Time Graphical Analysis Capability into a Monte Carlo Transport Code  

Procassini, Richard
Enhancements to the Combinatorial Geometry Particle Tracker in the Mercury Monte Carlo Transport Code: Embedded Meshed and Domain Decomposition  

Procassini, Richard
FZ2NC: A Tool for Monte Carlo Transport Code Geometry Manipulation  

Puente-Espel, Federico
Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels  

Pusa, Maria
Burnup Calculation Capability in the PSG2/Serpent Monte Carlo Reactor Physics Code  

Queiroz Filho, Pedro
Object Oriented Design of Anthropomorphic Phantoms and GEANT4-Based Implementations  

Quintieri, Lina
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Rabiti, Cristian
Recent Research Progress on UNIC at Argonne National Laboratory  

Rabiti, Cristian
Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics  

Ragusa, Jean
A Positive Nonlinear Closure for the Sn Equations with Linear Discontinuous Spatial Differencing  

Ragusa, Jean C.
Galerkin-Quadratures for the Sn Method in 2D Cartesian Geometries and Application to Forward-Peaked Scattering Particle Transport Problems  

Ragusa, Jean C.
Verification of Multiphysics Software: Space and Time Convergence Studies for Nonlinearly Coupled Applications  

Ragusa, Jean C.
Cross Section Inference Based on PDE-Constrained Optimization  

Ragusa, Jean C.
Spatial Adaptivity for Time-Dependent Diffusion Problems  

Ragusa, Jean C.
Goal-Oriented Mesh Adaptivity for Multi-Dimension SPN Equations  

Ragusa, Jean C.
A P1 Conforming DSA Scheme for DGFEM SN Transport  

Rahnema, Farzad
A Simplified 2D HTTR Benchmark Problem  

Rahnema, Farzad
2-Dimensional PWR and BWR Whole Core Benchmark Problems  

Rahnema, Farzad
A Hybrid Diffusion/Transport Method  

Rahnema, Farzad
A Perturbation Response Function Generation Method  

Ramet, Pierre
A Non Overlapping Parallel Domain Decomposition Method Applied to the Simplified Transport Equations  

Rapp, M.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Rapp, Michael
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Ravetto, Piero
Subcriticality Determination by Neural-Based Inversion of Space-Energy Neutron Kinetic Equations  

Ravetto, Piero
Variational Methods in the Kinetic Modeling of Nuclear Reactors: Recent Advances  

Ravnik, Matjaz
MCNP and Visualization of Neutron Flux and Power Distributions  

Reed, Michael S.
A Linear-Discontinuous Cut-Cell Discretization for the Sn Equations in R-Z Geometry  

Reitsma, Frederik
A Comparison of Pebble Mixing and Depletion Algorithms Used in Pebble-Bed Reactor Equilibrium Cycle Simulation  

Rhodes III, Joel D.
CASMO-5 Versus MCNP-5 Benchmark of Radial Power Profile in a Fuel Pin  

Ricci, Sophie
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Ricotti, Marco E.
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: Application to a Generation IV Lead Fast Reactor (LFR)  

Rineiski, Andrei
Implementation of a Plate-Type Fuel Model to a Multi-Physics Code and Benchmark Modeling of Special Power Excursion Reactor Tests  

Rising, Michael E.
A Diffusion Synthetic Accelerated Linear Discontinuous Version of the Spherical Geometry Method of Tubes  

Rizwan, Uddin
Modified Nodal Integral Method Incorporated with Irregular-Shape Elements for Navier-Stokes Equations  

Ro, Tae-Ik
Benchmark Experiment of Neutron Resonance Scattering Models in Monte Carlo Codes  

Roberts, Jeremy A.
Adjoint Current-Based Approaches to Prostate Brachytherapy Optimization  

Roblin, Philippe
Improved Thermal Modeling of a SNF Shipping-Cask Drying  

Rohde, Ulrich
Influence of the Neutron-Kinetic Feedback Parameter Variation on an Anticipated Transient without Scram in a PWR  

Roman, Jean
A Non Overlapping Parallel Domain Decomposition Method Applied to the Simplified Transport Equations  

Romano, Paul K.
Application of the Stochastic Oscillator to Assess Source Convergence in Monte Carlo Criticality Calculations  

Rosa, Massimiliano
Fourier Analysis of Cell-Wise Block-Jacobi Splitting in Two-Dimensional Geometry  

Rowe, Mireille A.
Assessment of Mark I Rod Irradiations in the UF Subcritical Water Tank Experiment Using Transport Methods  

Rowe, Mireille A.
Neutron Response of Silicon Carbide Semiconductor Detectors from Deterministic Adjoint Transport Calculations  

Ruggieri, Jean-Michel
High-Order Discrete Ordinate Transport in Non-Conforming 2D Cartesian Meshes  

Russ, William R.
Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries  

Russkov, Alexander A.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Russkov, Alexander A.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Ryzhikov, Gennady A.
Modeling of Radiation Transport in Coupled Atmosphere-Snow-Ice-Ocean Systems  

Saglime, F.
High Energy Neutron Time of Flight Measurements of Carbon and Beryllium Samples at the RPI LINAC  

Saglime, Frank, III
High Energy Neutron Scattering Benchmark of Monte Carlo Computations  

Sanchez, Richard
Convergence Analysis for the Method of Characteristics in Unstructured Meshes  

Sanchez, Richard
Neutronic Modeling for Pebble Bed Reactors  

Sanchez-Espinoza, V.H .
Development of a Coupling Scheme between MCNP and COBRA-TF for the Prediction of the Pin Power of a PWR Fuel Assembly  

Santamarina, Alain
Temperature Coefficient for PWR UO2 and MOX Lattices, Using 3D Transport Calculations and JEFF3.1.1 Library  

Santamarina, Alain
A 1st Order Formulation of a Reaction Rate Variation for Spatial and Energy Collapsing  

Santandrea, Simone
Convergence Analysis for the Method of Characteristics in Unstructured Meshes  

Santandrea, Simone
High Order Method of Characteristic for 2-D Unstructured Meshes  

Saracco, Paolo
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Sargeni, Antonio
A 1st Order Formulation of a Reaction Rate Variation for Spatial and Energy Collapsing  

Sarmento, Raul
Air Kerma Distribution in an Irradiation Facility - Comparison of Monte Carlo Simulations with Physical Dosimetry Measurements  

Sarotto, Massimo
Deterministic and Stochastic Approach for a Void Reactivity Effect Evaluation: Application to a Generation IV Lead Fast Reactor (LFR)  

Sartori, Enrico
Overview and Discussion of Phase I of the OECD LWR UAM Benchmark Activity  

Saurel, Richard
A Simple and Efficient Diffuse Interface Method for Compressible Two-Phase Flows  

Schaefer, Jason P.
Subspace Multi-SCALE Approach for Reactor Analysis, Part I: Energy Variable  

Schillebeeckx, Peter Jose
Calibration of the BC-523A Capture-Gated Liquid Scintillation Detector  

Schitthelm, Oliver
Monte-Carlo-Based Simulation of LWR Cores with Innovative Fuel Concepts  

Schulenberg, Thomas
Assessment of ERANOS for HPLWR Core Analyses  

Schulenberg, Thomas
Coupled ERANOS/TRACE System for HPLWR 3 Pass Core Analyses  

Schull, Mitchel A
Canopy Spectral Invariants: A New Concept in Remote Sensing of Vegetation  

Schulte, Reinhard
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Schunert, Sebastian
On the Adequacy of Cartesian Geometry Discrete Ordinates Solutions for Assembly Calculations  

Schunert, Sebastian
Verification and Validation of Deterministic Radiation Transport Numerical Methods, Codes, and Nuclear Data for Estimating Radiation Dose to Patients During CT Scan  

Searson, Keith
Importing CAD Models into MONK and MCBEND  

Secton, James
Dr. James Sexton (IBM) Advances in High Performance Computing - the IBM Perspective  

Serikov, Arkady
Use of McCad for the Generation of MCNP Models in Fusion Neutronics  

Seubert, Armin
Time-Dependent Anisotropic Distributed Source Capability in Transient 3-D Transport Code TORT-TD  

Seubert, Armin
Energy-Angle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion  

Shaver, Mark
Multi-Group Transport Methods for High-Resolution Neutron Activation Analysis  

Shearer, Micheal
Discrete Ordinate Mapping Algorithm for Region-Based Quadrature Sets  

Shearer, Micheal
Effective Software Design for a Deterministic Transport System  

Shearer, Micheal T.
Surface Mesh Refinement with the Slice Balance Approach (SBA)  

Shikota, Keiji
Development of Open Code System for BWR Lattice Calculation by Monte Carlo Method  

Shim, Hyung Jin
Monte Carlo Depletion and Uncertainty Analysis for a TRU Fuel Assembly Using JENDL3.3 Covariance Data  

Shim, Hyung Jin
Application of Inactive Cycle Stopping Criteria for Monte Carlo Wielandt Calculations  

Shkarovsky, Denis A.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Shrimpton, Paul C.
Development of PC Based Monte Carlo Simulations for the Calculation of Scanner-Specific Normalized Organ Doses from CT  

Shuttleworth, Edmund
Testing of the Tetrahedral Mesh Import Capability for Importing Converted CAD Files for Shielding and Criticality Calculations with MONK and MCBEND  

Siegel, Andrew
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Singh, Suneet
Modified Choke Flow Criterion for the Two-Phase Two-Fluid Model  

Sinitsa, Valentin
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Sjoden, Glenn E.
Assessment of Mark I Rod Irradiations in the UF Subcritical Water Tank Experiment Using Transport Methods  

Sjoden, Glenn E.
PWR Assembly Transport Calculation: a Validation Benchmark Using DRAGON, PENTRAN, and MCNP  

Sjoden, Glenn E.
Automatically Tuned Adaptive Differencing Algorithm for 3-D Sn Implemented in PENTRAN  

Sjoden, Glenn E.
Transport Methods Used for Homeland Security and Non-Proliferation Detection Applications: an Overview  

Sjoden, Glenn E.
Application of Electron Dose Kernels to Account for Heterogeneities in Voxelized Phantoms  

Sjoden, Glenn E.
Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications  

Sjoden, Glenn E.
Analysis and Benchmarking of PENTRAN Code using the OECD-NEA Benchmark Problems  

Sjoden, Glenn E.
Design of a Neutron Detector Array for SNM Optimized by Radiation Transport Methods  

Sjoden, Glenn E.
Neutron Response of Silicon Carbide Semiconductor Detectors from Deterministic Adjoint Transport Calculations  

Smedley-Stevenson, Richard
A Non-Linear Optimal Discontinuous Petrov-Galerkin Method for Stabilising the Solution of the Transport Equation  

Smedley-Stevenson, Richard P.
A Linear SIMC Scheme Suitable for Extension to Multi-Dimensions  

Smirnov, Oleg N.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Smith, Barry
Recent Research Progress on UNIC at Argonne National Laboratory  

Smith, Brandon M.
Acceleration Techniques for Direct Use of CAD-Based Geometries in Monte Carlo Radiation Transport  

Smith, Eric
Multi-Group Transport Methods for High-Resolution Neutron Activation Analysis  

Smith, Jeffrey
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Smith, Kord
CASMO-5 Versus MCNP-5 Benchmark of Radial Power Profile in a Fuel Pin  

Smith, Kord
Application of the Jacobian-Free Newton-Krylov Method in Computational Reactor Physics  

Smith, Micheal Addison
Recent Research Progress on UNIC at Argonne National Laboratory  

Smith, Micheal Addison
Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics  

Smith, Paul H.
An Analysis of Moment Preserving Methods for High Energy Ion Transport  

Snoj, Luka
MCNP and Visualization of Neutron Flux and Power Distributions  

Soler, Amparo
Qualification of the TH-3DNK Coupled Code RELAP5/PARCSv2.7 Against a BWR Unstable Point at Peach Bottom Nuclear Power Plant  

Solomon Jr., Clell J.
A Weighted Adjoint Source for Weight-Window Generation by Means of a Linear Tally Combination  

Sood, Avneet
A Weighted Adjoint Source for Weight-Window Generation by Means of a Linear Tally Combination  

Spaeh, Peter
Use of McCad for the Generation of MCNP Models in Fusion Neutronics  

Stamnes, Jakob
Modeling of Radiation Transport in Coupled Atmosphere-Snow-Ice-Ocean Systems  

Stamnes, Knut
Modeling of Radiation Transport in Coupled Atmosphere-Snow-Ice-Ocean Systems  

Stander, Gerhardt
An Automated Cross Section Parameterization Method for MTR Application  

Sternat, Mathew
Cross Section Inference Based on PDE-Constrained Optimization  

Su, Bingjing
Simulating Small Changes in System Response by MCNP5  

Sudhakar, Manju
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Sugimura, Naoki
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Sukharev, Yuriy P.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Sumaneev, Oleg V.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Suteau, Christophe
High-Order Discrete Ordinate Transport in Non-Conforming 2D Cartesian Meshes  

Sutton, Thomas M.
Instructive Concepts about the Monte Carlo Fission Source Distribution  

Sutton, Thomas M.
Comparison of Some Monte Carlo Models for Bound Hydrogen Scattering  

Tabuchi, Masato
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Taddeucci, Terry
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Tagziria, Hamid
Monte Carlo Modeling of Neutron Coincidence Counting Systems for Nuclear Safeguards  

Taitano, W
Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors  

Takeda, Toshikazu
Hybrid Method of MOC and Sn Nodal for PWR Core Analysis  

Talamo, Alberto
MCNPX and MCB Coupled Methodology for the Burnup Calculation of the KIPT Accelerator Driven Subcritical System  

Tarantola, Stefano
Application of Global Sensitivity Analysis Approach to Exercise I-1 of the OECD LWR UAM Benchmark  

Tatsumi, Masahiro
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Tatsumi, Masahiro
Study of the Acceleration of Nuclide Burnup Calculation Using GPU with CUDA  

Tautges, Timothy J.
Acceleration Techniques for Direct Use of CAD-Based Geometries in Monte Carlo Radiation Transport  

Taylor, J. Bryce
A Time-Dependent Method of Characteristics for 3D Nuclear Reactor Kinetics Applications  

Tessendorf, Jerry
Numerical Integration of the Feynman Path Integral for Radiative Transport  

Teunckens, Lucien
Spatial Meshing Effect and Reflector Treatment in PWR Core Modeling  

Teyssedou, Alberto
Achieving Negative Coolant-Void Reactivity in CANDU Generation III+  

Thomas, Justin W.
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Thomas, Justin W.
Multi-Resolution Modeling of Subassembly Pin Bundles for Advanced Fast Reactor Safety Simulations  

Thual , Olivier
Enhancement of Xenon Dynamical Forecasts for PWR Guiding Systems Using Variational Data Assimilation  

Todorova, Galina
TRIPOLI4 Solutions of VVER-1000 Assembly and Core Benchmarks  

Tokuhiro, Akira T.
Rans-Based CFD Simulations of Sodium Fast Reactor Wire-Wrapped Pin Bundles  

Tomasevic, Djordje I.
An Extension of the Multigroup Analytic Nodal Method (MANM) to Problems in Hexagonal-Z Geometry  

Tomatis, Daniele
Improvements and Core Applications of the Migration Mode Method  

Toth, Bryan E.
Noise Analysis of Smoothed Residual Acceleration, a Monte Carlo Neutron Source Convergence Algorithm  

Tovesson, Fredrik
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Trahan, Travis
Galerkin-Quadratures for the Sn Method in 2D Cartesian Geometries and Application to Forward-Peaked Scattering Particle Transport Problems  

Trama, Jean-Christophe Pierre
Importing CAD to TRIPOLI(R)  

Trumbull, Timothy
Comparison of Some Monte Carlo Models for Bound Hydrogen Scattering  

Tsige-Tamirat, Haileyesus
Use of McCad for the Generation of MCNP Models in Fusion Neutronics  

Tsige-Tamirat, Haileyesus
Current Status of the CAD Interface Program McCad for MC Particle Transport Codes  

Tsofin, Vladimir I.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Tucker, Julie D.
Determination of Solute-Interstitial Interactions in Ni-Cr by First Principles  

Turcksin, Bruno
Spatial Adaptivity for Time-Dependent Diffusion Problems  

Turcksin, Bruno
Goal-Oriented Mesh Adaptivity for Multi-Dimension SPN Equations  

Ueki, Taro
Instructive Concepts about the Monte Carlo Fission Source Distribution  

Ueki, Taro
The Appearance of Complex Values in Monte Carlo Calculation of Degenerate Eigenvalues  

Ullmann, John
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Ünlü, Kenan
A Case Study to Test MOZAIK for Different Optimization Problems  

Ushio, Tadashi
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Van Criekingen, Serge
Domain Decomposition Parallelization of Neutron Transport Calculations  

Van Riper, Kenneth A.
Moritz Enhancements for Visualization of Complicated Geometry Models  

Varnai, Tamas
Modeling and Analysis of Offbeam Lidar Returns from Thick Clouds, Snow, and Sea Ice  

Vasques, Richard
Anisotropic Diffusion in Model 2-D Pebble-Bed Reactor Cores  

Vaz, Pedro
Air Kerma Distribution in an Irradiation Facility - Comparison of Monte Carlo Simulations with Physical Dosimetry Measurements  

Velkov, Kiril
Generation of Consistent Conservative Cross Section Data for the Coupled System Code ATHLET-QUABOX/CUBBOX  

Velkov, Kiril
Uncertainty Analysis of COBRA-TF Void Distribution Predictions for the OECD/NRC BFBT Benchmark  

Venkataramen, Ram
Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries  

Verdu Martin, Gumersindo
Qualification of the TH-3DNK Coupled Code RELAP5/PARCSv2.7 Against a BWR Unstable Point at Peach Bottom Nuclear Power Plant  

Verdu, Gumersindo
Spectral Element Method for the Neutron Diffusion Equation on a Triangular Mesh  

Veron, Dana
Markovian Approach: from Ising Model to Stochastic Radiative Transfer  

Vialle, Stéphane
Massively Parallel Solving of 3D Simplified Pn Equations on Graphics Processing Units  

Visonneau, Thierry
TRIPOLI4 Solutions of VVER-1000 Assembly and Core Benchmarks  

Vlachoudis, Vasilis
FLAIR: A Powerful but User Friendly Graphical Interface for FLUKA  

Voloschenko, Andrei M.
The CNCSN-2: One, Two and Three-Dimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System  

Voloschenko, Andrei M.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Wachspress, Eugene L.
Generalized Finite Elements  

Wagner, John
Forward-Weighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities  

Wagner, John
Automated Weight-Window Generation for Threat Detection Applications Using ADVANTG  

Wang, Kan
The Linear Source Approximation in Three Dimension Characteristics Method  

Wang, Yaqi
A P1 Conforming DSA Scheme for DGFEM SN Transport  

Warsa, James
Fourier Analysis of Cell-Wise Block-Jacobi Splitting in Two-Dimensional Geometry  

Warsa, James
Negative Flux Fixups in Discontinuous Finite Element SN Transport  

Warsa, James S.
Time-Step Limits for a Monte Carlo Compton-Scattering Method  

Warsa, James S.
A Piecewise Linear Discontinuous Finite Element Spatial Discretization of the Transport Equation in 2D Cylindrical Geometry  

Warsa, James S.
Stochastic Methods for Uncertainty Quantification in Radiation Transport  

Watchman, C.
Dose Verification for Accelerated Partial Breast Irradiation  

Waters, Laurie S.
MCNPX Graphics and Arithmetic Tally Upgrades  

Watson, Aaron M.
Effective Software Design for a Deterministic Transport System  

Watson, Aaron M.
Discrete Ordinate Mapping Algorithm for Region-Based Quadrature Sets  

Watson, Aaron M.
Coupled Energy Group Iteration Scheme for Deterministic Transport Problems  

Watts, David Garland
Comparison of MCNP and WIMS-AECL/RFSP Calculations against Critical Heavy Water Experiments in ZED-2 with CANFLEX-LVRF and CANFLEX-LEU Fuels  

Weidenspointner, Georg
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Weiss, F. P.
On the Influence of Spatial Discretization in LWR Steady State and Burnup Calculations with HELIOS 1.9  

Weiss, F.P.
An Analytical Solution for an External Source Problem with Delayed Neutrons Using the Telegraphers Equation  

Weiss, Frank-Peter
Influence of the Neutron-Kinetic Feedback Parameter Variation on an Anticipated Transient without Scram in a PWR  

Wender, Stephen A.
Improving the Nuclear Data Base for Non-Proliferation and Homeland Security  

Wenner, Michael T.
A Combined Diagnostic Approach for Monte Carlo Source Convergence Identification  

Wieselquist, William Adam
A Quasidiffusion Method for Unstructured Quadrilateral Meshes in 2D XY Geometry  

Wilhelm, Dirk
Implementation of a Plate-Type Fuel Model to a Multi-Physics Code and Benchmark Modeling of Special Power Excursion Reactor Tests  

Williams, Mark
An Ultra-Fine Group Slowing Down Benchmark  

Williams, Mark L.
Development of Generalized Perturbation Theory Capability within the SCALE Code Package  

Wilson, Paul P. H.
Acceleration Techniques for Direct Use of CAD-Based Geometries in Monte Carlo Radiation Transport  

Wilson, Steve C.
Rejection Sampling from a Spherical Harmonics Angular Flux Functional Expansion for a Discrete Ordinates to Monte Carlo Splice  

Wollaber, A.
Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics  

Wollaber, Allan
A Hybrid Monte Carlo-Deterministic Approach to Improve the Accuracy and Efficiency of Monte Carlo Calculations for Thermal Radiative Transfer  

Wollaber, Allan B.
A Linear Stability Analysis for Nonlinear, 1-D, Gray Implicit Monte Carlo Calculations  

Wollaber, Allan B.
A Time-Dependent Fleck Factor to Enhance the Accuracy of the Implicit Monte Carlo Equations  

Wollaber, Allan
Recent Research Progress on UNIC at Argonne National Laboratory  

Wolters, Emily R.
A Hybrid Monte Carlo-S2 Method for Preserving Neutron Transport Effects  

Wroe, Andrew
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Wu, Yican
CAD-Based Modeling for 3-D Particle Transport  

Xu, Liang
Canopy Spectral Invariants: A New Concept in Remote Sensing of Vegetation  

Xu, X. George
Multidetector CT (MDCT) Modeling for Organ Dose Assessments of Various Patient Phantoms  

Xu, X. George
Deformable and Posture-Changeable Computational Phantoms and Dosimetry Data for Standard External-Beam Irradiations  

Xu, Xie George
Applications of Monte Carlo Computational Framework of a Medical Accelerator Used for Radiation Treatment  

Xu, Xie George
A Project to Design a Software Package for Reporting Multidetector CT (MDCT) Doses  

Xu, Zhiwen
CASMO-5 Versus MCNP-5 Benchmark of Radial Power Profile in a Fuel Pin  

Yamaji, Kazuya
Hybrid Method of MOC and Sn Nodal for PWR Core Analysis  

Yamamoto, Akio
Verification of the Resonance Calculation Model for Rod Cluster Control Based on Ultra-Fine-Group Spectrum Calculation in the AEGIS Code  

Yang, Jinan
Application of the 'Functional Monte Carlo' Method to Estimate Continuous Energy k-Eigenvalues and Eigenfunctions  

Yang, Won Sik
Recent Research Progress on UNIC at Argonne National Laboratory  

Yang, Won Sik
Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics  

Yao, Dong
The Linear Source Approximation in Three Dimension Characteristics Method  

Yesilyurt, Gokhan
On-the-Fly Doppler Broadening for Monte Carlo Codes  

Yi, Ce
Analysis of SPECT Imaging Simulation Using the TITAN Transport Code  

Yi, Ce
Hybrid Sn and Ray-Tracing with Fictitious Quadrature for Simulation of SPECT  

Yi, Ce
Accuracy of TITAN Based on a New OECD-NEA Benchmark over a Range in Parameter Space  

Yi, Ce
Automatically Tuned Adaptive Differencing Algorithm for 3-D Sn Implemented in PENTRAN  

Yi, Ce
Analysis and Benchmarking of PENTRAN Code using the OECD-NEA Benchmark Problems  

Yoo, Jae-Woon
Benchmark Analysis of a Metallic Plutonium Fueled BFS-55-1 Critical Assembly  

Yoo, Jae-Woon
Breakeven Core Design Studies for a Sodium Cooled Fast Reactor  

Yoon, Joo Il
Investigation of Multigroup Effect in Transient Calculation to Determine Hottest Pin Enthalpy  

Yoshikawa, Takamichi
Development of Open Code System for BWR Lattice Calculation by Monte Carlo Method  

Yun, Sunghwan
Monte Carlo Anchoring Method for Loosely-Coupled k-Eigenvalue Problem  

Zankl, Maria
Development of PC Based Monte Carlo Simulations for the Calculation of Scanner-Specific Normalized Organ Doses from CT  

Zaritsky, Sergei M.
Experience in the Use of the Monte-Carlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations  

Zeller, Michael
Comparison of MCNP and WIMS-AECL/RFSP Calculations against Critical Heavy Water Experiments in ZED-2 with CANFLEX-LVRF and CANFLEX-LEU Fuels  

Zeng, Qin
CAD-Based Modeling for 3-D Particle Transport  

Zerovnik, Gašper
MCNP and Visualization of Neutron Flux and Power Distributions  

Zerr, Robert Joseph
A Parallel Algorithm for Solving the Integral Form of the Discrete Ordinates Equations  

Zhang, Baocheng
The WhiteStar Development Project: Westinghouse’s Next Generation Core Design Simulator and Core Monitoring Software to Power the Nuclear Renaissance  

Zhang, Dingkang
A Simplified 2D HTTR Benchmark Problem  

Zhang, Dingkang
A Hybrid Diffusion/Transport Method  

Zhang, Dingkang
A Perturbation Response Function Generation Method  

Zhang, Juying
Deformable and Posture-Changeable Computational Phantoms and Dosimetry Data for Standard External-Beam Irradiations  

Zhang, Zhan
A Simplified 2D HTTR Benchmark Problem  

Zhong, Zhaopeng
MCNPX and MCB Coupled Methodology for the Burnup Calculation of the KIPT Accelerator Driven Subcritical System  

Zimin, Aleksandr A.
Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility  

Zoglauer, Andreas
R&D for Co-Working Condensed and Discrete Transport Methods in GEANT4 Kernel  

Zwermann, Winfried
Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations