

Author Index (for Papers on the CD)




AbdelKhalik, Hany S. Subspace MultiSCALE 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. SemiConsistent 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 PinbyPin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations 
AlBasheer, Ahmad Application of Electron Dose Kernels to Account for Heterogeneities in Voxelized Phantoms 
AlBasheer, Ahmad Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications 
Alexandrov, Michael Inversion of MultiAngle Radiation Measurements 
AlHamry, A. Development of a Coupling Scheme between MCNP and COBRATF for the Prediction of the Pin Power of a PWR Fuel Assembly 
Allelein, H. J. MonteCarloBased Simulation of LWR Cores with Innovative Fuel Concepts 
Allen, Todd Determination of SoluteInterstitial Interactions in NiCr by First Principles 
Ambers, Scott Analytical Description of Pulses Measured with an Organic Liquid Scintillator for Pulse Shape Discrimination 
Anistratov, Dmitriy Y. MultiLevel 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 PinbyPin Core Analysis Method Using ThreeDimensional Direct Response Matrix 
Aragones, J. M. Development and Performance of the ANDES/COBRAIII Coupled System in HexagonalZ Geometry 
Aragonés, JoséMaría Performance of Whole Core PinbyPin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations 
Argaud, JeanPhillippe 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 MultiGrid Genetic Algorithms for Space Shield Design 
Assawaroongruengchot, Monchai Validating Models for Coolant Void Reactivity Evaluation in CANDU Generation III+ 
Augelli, Mauro R&D for CoWorking 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 COBRATF 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 MultiPhysics 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 JacobianFree NewtonKrylov 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 DiscreteOrdinates Transport Sweep Algorithms with Collisions 
Baker, Randal S. Deterministic Methods for TimeDependent 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 TimeDependent Method of Characteristics for 3D Nuclear Reactor Kinetics Applications 
Barbu, Anthony SemiConsistent 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 TH3DNK 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 ThermalhydraulicNeutronic 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 CoarseMesh Spectral Nodal Solution of SlabGeometry 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, AnneMarie 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 EnergyAngle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion 
Becker, Maarten TimeDependent Anisotropic Distributed Source Capability in Transient 3D Transport Code TORTTD 
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 GEANT4Based Implementations 
Begalli, Marcia R&D for CoWorking 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 SelfShielding Models to CriticalitySafety 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 TwoPhase Flows 
Bess, John Darrell Preliminary Benchmark Evaluation of Japan’s High Temperature Engineering Test Reactor 
Bhat, Ishwara Optimization of a Novel SolidState 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 AtmosphereSnowIceOcean Systems 
Bitteker, Leo J. Improving the Nuclear Data Base for NonProliferation and Homeland Security 
Blakeman, Ed D ForwardWeighted 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 WeightWindow 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 SUHAM3D 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. LevermorePomraning 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 EnergyAngle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion 
Bromley, Blair P. Comparison of MCNP and WIMSAECL/RFSP Calculations against Critical Heavy Water Experiments in ZED2 with CANFLEXLVRF and CANFLEXLEU 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 kEigenvalue Calculations 
Brown, Forrest B. A Review of Monte Carlo Criticality Calculations  Convergence, Bias, Statistics 
Brown, Forrest B. OntheFly Doppler Broadening for Monte Carlo Codes 
Bruna, G. Implementation of a PlateType Fuel Model to a MultiPhysics 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 NonLinear Optimal Discontinuous PetrovGalerkin Method for Stabilising the Solution of the Transport Equation 
Burns, Kimberly MultiGroup Transport Methods for HighResolution Neutron Activation Analysis 
Cahalan, Robert F. Modeling and Analysis of Offbeam Lidar Returns from Thick Clouds, Snow, and Sea Ice 
Cairns, Brian Inversion of MultiAngle 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 MultiAngle 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 CoolantVoid 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 PredictorCorrector Methods 
Cho, Nam Zin Extension of Generating NonNegative Scattering CrossSections for Two Dimensional Geometry 
Cho, Nam Zin Monte Carlo Anchoring Method for LooselyCoupled kEigenvalue Problem 
Christoforou, Stavros Using a ZeroVariance 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 2D Unstructured Meshes 
Clifford, Ivor David The Application of a MultiPhysics Toolkit to Spatial Reactor Dynamics 
Colmont, Didier A. Improved Thermal Modeling of a SNF ShippingCask 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 3D Sn Implemented in PENTRAN 
Couture, Aaron J. Improving the Nuclear Data Base for NonProliferation and Homeland Security 
Cowan, Pat Importing CAD Models into MONK and MCBEND 
Crawford, Martin J. A WeightWindow Generator for ElectronPhoton Transport in the Integrated TIGER Series Codes 
da Cruz, D. F. MonteCarloBased 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 TimeDependent Anisotropic Distributed Source Capability in Transient 3D Transport Code TORTTD 
Dagan, Ron EnergyAngle 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 SolidState 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 ATUCHA2 PHWR Monte Carlo MCNP5 and KENOVI Models Development and Application 
Davidson, Gregory G. Sweepless TimeDependent 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 MultiPhysics Coupling of Neutron Diffusion and Thermomechanics in Spherical Fast Burst Reactors 
de Queiroz Filho, Pedro Pacheco R&D for CoWorking Condensed and Discrete Transport Methods in GEANT4 Kernel 
de Souza e Silva, Rosana Object Oriented Design of Anthropomorphic Phantoms and GEANT4Based Implementations 
de Souza Santos, Denison R&D for CoWorking Condensed and Discrete Transport Methods in GEANT4 Kernel 
de SouzaSantos, Denison Object Oriented Design of Anthropomorphic Phantoms and GEANT4Based 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. TimeStep Limits for a Monte Carlo ComptonScattering 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 NonProliferation and Homeland Security 
Ding, Aiping A Project to Design a Software Package for Reporting Multidetector CT (MDCT) Doses 
Ding, Aiping Deformable and PostureChangeable Computational Phantoms and Dosimetry Data for Standard ExternalBeam Irradiations 
Dingley, Justin Optimization of a Novel SolidState 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 MonteCarlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations 
Do, JeanMichel Fuel Loading Pattern for Heterogeneous EPR Core Configuration Using a Distributed Evolutionary Algorithm 
Douglass, Steven J. 2Dimensional 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 OrderConvergence Anomalies in SecondOrder Finite Elements Transport Methods 
Dubinin, Anatoly A. The CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
Dulla, Sandra Subcriticality Determination by NeuralBased Inversion of SpaceEnergy 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 MultiPurpose Code for Core Physics Analysis 
Dweiri, Yousif Comparison of MCNP and WIMSAECL/RFSP Calculations against Critical Heavy Water Experiments in ZED2 with CANFLEXLVRF and CANFLEXLEU Fuels 
Eaton, M A NonLinear Optimal Discontinuous PetrovGalerkin 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 CrossSection Generation Model in the Fast Code System and its Application to the GenIV GasCooled 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 I1 of the OECD LWR UAM Benchmark 
Evans, Thomas M. A Monte Carlo Synthetic Acceleration Method for the NonLinear, TimeDependent Diffusion Equation 
Evans, Thomas M. Automated WeightWindow Generation for Threat Detection Applications Using ADVANTG 
Falgout, Robert D. Analysis of Massively Parallel DiscreteOrdinates 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. RansBased CFD Simulations of Sodium Fast Reactor WireWrapped Pin Bundles 
Fanning, Thomas H. MultiResolution 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 CoolantVoid Reactivity in CANDU Generation III+ 
Fernex, Frederic Application of Advanced SelfShielding Models to CriticalitySafety 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 CoarseMesh Spectral Nodal Solution of SlabGeometry Sn Transport Problems 
Fischer, Paul F. RansBased CFD Simulations of Sodium Fast Reactor WireWrapped 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 BC523A CaptureGated 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 2Dimensional PWR and BWR Whole Core Benchmark Problems 
Forslund Guimaraes, Petri Parameterization of TwoGroup Nodal Cross Section Data for POLCAT BWR Transient Applications 
Forslund Guimaraes, Petri Development of New Pin Power Recovery Methodology 
Fotiades, Nikolaos Improving the Nuclear Data Base for NonProliferation and Homeland Security 
Fougeras, Philippe APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic MultiPurpose Code for Core Physics Analysis 
Fournier, Damien Adaptive Algorithms for a SelfShielding WaveletBased Galerkin Method 
Fournier, Damien HighOrder Discrete Ordinate Transport in NonConforming 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 TwoDimensional Whole Core Transport Calculations Using PARAGON 
Franke, Brian C. An hpAdaptivity Approach for Monte Carlo Tallies 
Franke, Brian C. A WeightWindow Generator for ElectronPhoton 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 NeuralBased Inversion of SpaceEnergy Neutron Kinetic Equations 
Gabrielli, F. Implementation of a PlateType Fuel Model to a MultiPhysics 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 NeuralBased Inversion of SpaceEnergy Neutron Kinetic Equations 
Ganapol, Barry Douglas Dose Verification for Accelerated Partial Breast Irradiation 
Ganapol, Barry Douglas An UltraFine Group Slowing Down Benchmark 
GarciaHerranz, N. Development and Performance of the ANDES/COBRAIII Coupled System in HexagonalZ Geometry 
Gargioni, Elisabetta R&D for CoWorking 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 HighOrder Discrete Ordinate Transport in NonConforming 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 NonProliferation and Homeland Security 
Gentile, Nick Implicit Monte Carlo Radiation Transport in MultiPhysics Simulations 
Gesh, Christopher John MultiGroup Transport Methods for HighResolution 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 NonProliferation 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 I1 of the OECD LWR UAM Benchmark 
Ghrayeb, Shadi Improving Burnup Performance of Fast Sodium Cooled Reactor by Utilizing Thorium Based Fuels 
Gil, ChoongSup Benchmark Analysis of a Metallic Plutonium Fueled BFS551 Critical Assembly 
Gill, Daniel Fury A JacobianFree NewtonKrylov 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 GodivaIV DelayedCritical and SuperPromptCritical Conditions 
Gohar, Yousry MCNPX and MCB Coupled Methodology for the Burnup Calculation of the KIPT Accelerator Driven Subcritical System 
Gol'din, Vladimir Ya. MultiLevel 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 MultiPurpose 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 PebbleBed 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 NonExtinction Probability for Prompt Critical Systems 
Griesheimer, David P. Analysis of Distances between Inclusions in Finite OneDimensional 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 CoWorking Condensed and Discrete Transport Methods in GEANT4 Kernel 
Grove, Robert E. Discrete Ordinate Mapping Algorithm for RegionBased 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 ShippingCask Drying 
Gukov, Sergei V. The CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
Gurevich, Michael I. The CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
Gurevich, Michael I. Experience in the Use of the MonteCarlo 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 PinPower Calculation against Experimental VVERFullCore Benchmark 
Haghighat, Alireza Analysis and Benchmarking of PENTRAN Code using the OECDNEA Benchmark Problems 
Haghighat, Alireza Hybrid Sn and RayTracing with Fictitious Quadrature for Simulation of SPECT 
Haghighat, Alireza Accuracy of TITAN Based on a New OECDNEA 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 NonProliferation 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 AtmosphereSnowIceOcean 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 SelfShielding Models to CriticalitySafety 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 CurrentBased Approaches to Prostate Brachytherapy Optimization 
Henderson, Douglass L. Acceleration Techniques for Direct Use of CADBased Geometries in Monte Carlo Radiation Transport 
Herrero, JoséJavier Performance of Whole Core PinbyPin Calculations by Domain Decomposition through Alternate Dissections in Steady State and Transient Calculations 
Hesse, Ulrich DORTOREST: A Coupled TransportDepletion Code System for LWR Fuel Assembly Burnup Calculations 
Hill, Tony Improving the Nuclear Data Base for NonProliferation and Homeland Security 
Hino, Tetsushi Development of PinbyPin Core Analysis Method Using ThreeDimensional Direct Response Matrix 
Hiruta, Hikaru Analysis of an EarthquakeInitiatedTransient in a PBR 
Holloway, James P. MultiGrid Genetic Algorithms for Space Shield Design 
Holloway, James P. A QuasiStatic Closure for 3rd Order Spherical Harmonics TimeDependent Radiation Transport in 2D 
Holloway, James P. Relaxation Scheme for Monte Carlo Explicitly Restarted Arnoldi’s Method for Criticality Calculations 
Holloway, James Paul Radiative Transfer with Monte Carlo PredictorCorrector 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 ZeroVariance 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 IrregularShape Elements for NavierStokes Equations 
Hugot, FrancoisXavier TRIPOLI4 Solutions of VVER1000 Assembly and Core Benchmarks 
Hugot, FrancoisXavier Use of TRIPOLI4.5 Mesh Tally to Investigate Power Maps of the LEUCOMPTHERM008 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 PinbyPin Core Analysis Method Using ThreeDimensional Direct Response Matrix 
Ivanov, Kostadin Uncertainty Analysis of COBRATF Void Distribution Predictions for the OECD/NRC BFBT Benchmark 
Ivanov, Kostadin Application of Global Sensitivity Analysis Approach to Exercise I1 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 MultiPhysics 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 ScannerSpecific Normalized Organ Doses from CT 
Jarrell, Joshua Discrete Ordinate Mapping Algorithm for RegionBased Quadrature Sets 
Jasak, Hrvoje The Application of a MultiPhysics 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/COBRAIII Coupled System in HexagonalZ Geometry 
Jiménez, Javier Performance of Whole Core PinbyPin 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 ThreeDimensional Core Calculations 
Joo, Han Gyu Investigation of Multigroup Effect in Transient Calculation to Determine Hottest Pin Enthalpy 
Joo, HyungKook 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 PebbleBed Reactor Equilibrium Cycle Simulation 
Joy, Kenneth Mercury + VisIt: Integration of a RealTime 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 ThermalhydraulicNeutronic Nuclear Power Plant Simulations 
Jung, Yeon Sang Decoupled Planar MOC Solution for Dynamic Group Constant Generation in Direct ThreeDimensional Core Calculations 
Kadioglu, Samet Y. Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors 
Kadioglu, Samet Y. Analysis and Numerical Solution for MultiPhysics 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. OrderofConvergence Study of a CondensedHistory Algorithm Implementation 
Keller, Katherine Analysis of SPECT Imaging Simulation Using the TITAN Transport Code 
Kelley, Timothy Fourier Analysis of CellWise BlockJacobi Splitting in TwoDimensional Geometry 
Kelsey, Charles T. IV Multigroup Neutron Dose Calculations for Proton Therapy 
Kensek, Ronald P. A WeightWindow Generator for ElectronPhoton Transport in the Integrated TIGER Series Codes 
Kensek, Ronald P. An hpAdaptivity Approach for Monte Carlo Tallies 
Kensek, Ronald P. OrderofConvergence Study of a CondensedHistory Algorithm Implementation 
Kiedrowski, Brian C. An Information Theory Based Analysis of Fission Source Correlation in Monte Carlo kEigenvalue Calculations 
Kim, Chan Hyeong R&D for CoWorking 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 BFS551 Critical Assembly 
Kim, Jae Hak Investigation of Multigroup Effect in Transient Calculation to Determine Hottest Pin Enthalpy 
Kim, Jong Woon Extension of Generating NonNegative Scattering CrossSections for Two Dimensional Geometry 
Kim, SangJi Benchmark Analysis of a Metallic Plutonium Fueled BFS551 Critical Assembly 
Kim, YeongIl 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 NeutronKinetic 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 MultiAngle Radiation Measurements 
Knoll, Dana Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors 
Knoll, Dana Analysis and Numerical Solution for MultiPhysics Coupling of Neutron Diffusion and Thermomechanics in Spherical Fast Burst Reactors 
Knoll, Dana Application of the JacobianFree NewtonKrylov 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 VVER1000 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 CADBased Geometries in Monte Carlo Radiation Transport 
Kraftcheck, Jason A. A WeightWindow Generator for ElectronPhoton Transport in the Integrated TIGER Series Codes 
Kryuchkov, Vyacheslav P. The CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
KrzykaczHausmann, Bernard Uncertainty Analysis of COBRATF Void Distribution Predictions for the OECD/NRC BFBT Benchmark 
Kucukboyaci, Vefa N. TwoDimensional 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 MultiAngle 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 ATHLETQUABOX/CUBBOX 
Laptev, Alexander Improving the Nuclear Data Base for NonProliferation and Homeland Security 
Larsen, Edward W. A Hybrid Monte CarloS2 Method for Preserving Neutron Transport Effects 
Larsen, Edward W. A Linear Stability Analysis for Nonlinear, 1D, Gray Implicit Monte Carlo Calculations 
Larsen, Edward W. A TimeDependent 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 CarloDeterministic Approach to Improve the Accuracy and Efficiency of Monte Carlo Calculations for Thermal Radiative Transfer 
Larsen, Edward W. Sweepless TimeDependent Transport Calculations Using the Staggered Block Jacobi Method 
Larsen, Edward W. Anisotropic Diffusion in Model 2D PebbleBed Reactor Cores 
Larsen, Edward W. Application of the 'Functional Monte Carlo' Method to Estimate Continuous Energy kEigenvalues and Eigenfunctions 
Lathuiliere, Bruno A Non Overlapping Parallel Domain Decomposition Method Applied to the Simplified Transport Equations 
Lautard, JeanJacques APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic MultiPurpose Code for Core Physics Analysis 
Lautard, JeanJacques Fuel Loading Pattern for Heterogeneous EPR Core Configuration Using a Distributed Evolutionary Algorithm 
Le Tellier, Romain HighOrder Discrete Ordinate Transport in NonConforming 2D Cartesian Meshes 
Le Tellier, Romain Adaptive Algorithms for a SelfShielding WaveletBased Galerkin Method 
Le Texier, P. Importing CAD to TRIPOLI(R) 
LebrunGrandie, Damien Tightly Coupled Multiphysics Simulations for Pebble Bed Reactors 
Lee, C. Deterministic Radiation Transport Simulations for Diagnostic Imaging Applications 
Lee, KiBog Breakeven Core Design Studies for a Sodium Cooled Fast Reactor 
Lee, YiKang Use of TRIPOLI4.5 Mesh Tally to Investigate Power Maps of the LEUCOMPTHERM008 PWR Critical Lattices 
Lee, YoungOuk Benchmark Analysis of a Metallic Plutonium Fueled BFS551 Critical Assembly 
Lee,YoungOuk Extension of Generating NonNegative Scattering CrossSections 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 MultiPurpose 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 WholeCore Neutron Transport Without Spatial Homogenization 
LiCausi, Nicholas Optimization of a Novel SolidState 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 PlateType Fuel Model to a MultiPhysics 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 EnergyAngle 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. TimeStep Limits for a Monte Carlo ComptonScattering Method 
Lozano Montero, Juan Andres Development and Performance of the ANDES/COBRAIII Coupled System in HexagonalZ Geometry 
Lu, JianQiang Optimization of a Novel SolidState Self Powered Neutron Detector 
Lu, Lei CADBased Modeling for 3D Particle Transport 
Macian, Rafael Uncertainty and Sensitivity Analysis in the Neutronic Parameters Generation over the Coupled ThermalhydraulicNeutronic Nuclear Power Plant Simulations 
Magat, Philippe APOLLO3: A Common Project of CEA, AREVA and EDF for the Development of New Deterministic MultiPurpose 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 UltraFine 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 3D Sn Implemented in PENTRAN 
Manturov, Gennady N. Experience in the Use of the MonteCarlo 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 CoolantVoid 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 SelfShielding Models to CriticalitySafety Studies 
Martin, William R. OntheFly 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 CarloS2 Method for Preserving Neutron Transport Effects 
Martin, William R. Radiative Transfer with Monte Carlo PredictorCorrector 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 MultiPurpose Code for Core Physics Analysis 
Martins, Maximiano Object Oriented Design of Anthropomorphic Phantoms and GEANT4Based Implementations 
Maschek, Werner Implementation of a PlateType Fuel Model to a MultiPhysics 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 2D 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 ATUCHA2 PHWR Monte Carlo MCNP5 and KENOVI 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 MultiGroup Cross Section Libraries for Analysis of LeadCooled 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 NonLinear Optimal Discontinuous PetrovGalerkin Method for Stabilising the Solution of the Transport Equation 
Mihailescu, Liviu Cristian Calibration of the BC523A CaptureGated Liquid Scintillation Detector 
Mikityuk, Konstantin A New CrossSection Generation Model in the Fast Code System and its Application to the GenIV GasCooled 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 CoarseMesh Spectral Nodal Solution of SlabGeometry Sn Transport Problems 
Miller, Eric Monte Carlo Simulation of the Full Multiplicity Distributions Measured with a Passive Counter 
Miller, Thomas M. Automated WeightWindow Generation for Threat Detection Applications Using ADVANTG 
Millman, David L. Analysis of Distances between Inclusions in Finite OneDimensional Binary Stochastic Materials 
MineevWeinstein, Mark Radiation Transport Through Random Media Represented as Measurable Functions: Positive Versus Negative Spatial Correlations 
Miró, Rafael Qualification of the TH3DNK 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 ThermalhydraulicNeutronic 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 SelfShielding Models to CriticalitySafety Studies 
Mitsuyasu, Takeshi Development of PinbyPin Core Analysis Method Using ThreeDimensional Direct Response Matrix 
Mittag, Siegfried Influence of the NeutronKinetic Feedback Parameter Variation on an Anticipated Transient without Scram in a PWR 
Mittag, Siegfried Validation of DYN3D PinPower Calculation against Experimental VVERFullCore 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 GalerkinQuadratures for the Sn Method in 2D Cartesian Geometries and Application to ForwardPeaked Scattering Particle Transport Problems 
Morel, Jim E. A LinearDiscontinuous CutCell Discretization for the Sn Equations in RZ Geometry 
Morgan, Dane Determination of SoluteInterstitial Interactions in NiCr by First Principles 
Mori, Masaaki Verification of the Resonance Calculation Model for Rod Cluster Control Based on UltraFineGroup Spectrum Calculation in the AEGIS Code 
Mosher, Scott W. Automated WeightWindow Generation for Threat Detection Applications Using ADVANTG 
Mosher, Scott W. A Monte Carlo Synthetic Acceleration Method for the NonLinear, TimeDependent Diffusion Equation 
Mosteller, Russell D. Analysis of GodivaIV DelayedCritical and SuperPromptCritical Conditions 
Mousseau, Vincent Modified Choke Flow Criterion for the TwoPhase TwoFluid 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 HexagonalZ Geometry 
Muller, Erwin Parameterization of TwoGroup Nodal Cross Section Data for POLCAT BWR Transient Applications 
Mureithi, Njuki William Achieving Negative CoolantVoid Reactivity in CANDU Generation III+ 
Na, Yong Hum Deformable and PostureChangeable Computational Phantoms and Dosimetry Data for Standard ExternalBeam Irradiations 
Nabbi, Rahim MonteCarloBased Simulation of LWR Cores with Innovative Fuel Concepts 
Najafabadi, Reza Determination of SoluteInterstitial Interactions in NiCr 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 NonProliferation 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 RealTime Graphical Analysis Capability into a Monte Carlo Transport Code 
O'Donnell, John M. Improving the Nuclear Data Base for NonProliferation and Homeland Security 
Oh, Kyeong S. A QuasiStatic Closure for 3rd Order Spherical Harmonics TimeDependent Radiation Transport in 2D 
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 UltraFineGroup Spectrum Calculation in the AEGIS Code 
Okui, Shota Study of the Acceleration of Nuclide Burnup Calculation Using GPU with CUDA 
Olekhnovitch, Andrei Achieving Negative CoolantVoid Reactivity in CANDU Generation III+ 
Oleynik, Dmitry S. Experience in the Use of the MonteCarlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations 
Oliveira, Francisco Bruno Analytical Reconstruction Schemes for CoarseMesh Spectral Nodal Solution of SlabGeometry Sn Transport Problems 
Ortensi, Javier Improved Prediction of the Doppler Effect in TRISO Fuel 
Ortensi, Javier Analysis of an EarthquakeInitiatedTransient 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 EarthquakeInitiatedTransient 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 TwoDimensional Whole Core Transport Calculations Using PARAGON 
Pain, Chris A NonLinear Optimal Discontinuous PetrovGalerkin 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. LevermorePomraning 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 ATUCHA2 PHWR Monte Carlo MCNP5 and KENOVI 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 JacobianFree NewtonKrylov Method in Computational Reactor Physics 
Pautz, Andreas DORTOREST: A Coupled TransportDepletion Code System for LWR Fuel Assembly Burnup Calculations 
Pautz, Andreas Uncertainty Analysis of COBRATF Void Distribution Predictions for the OECD/NRC BFBT Benchmark 
Pautz, Andreas Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations 
Pautz, Andreas TimeDependent Anisotropic Distributed Source Capability in Transient 3D Transport Code TORTTD 
Pautz, Andreas EnergyAngle 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 ATUCHA2 PHWR Monte Carlo MCNP5 and KENOVI 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 CrossSection Generation Model in the Fast Code System and its Application to the GenIV GasCooled 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 WIMSAECL/RFSP Calculations against Critical Heavy Water Experiments in ZED2 with CANFLEXLVRF and CANFLEXLEU 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 ForwardWeighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities 
Perin, Yann Uncertainty Analysis of COBRATF Void Distribution Predictions for the OECD/NRC BFBT Benchmark 
Petitpas, Fabien A Simple and Efficient Diffuse Interface Method for Compressible TwoPhase Flows 
Petrie, Lester M. Jr. Criticality Accident Alarm System Modeling with SCALE 
Petrov, Nikolay TRIPOLI4 Solutions of VVER1000 Assembly and Core Benchmarks 
Petrovic, Bojan Benchmarking of the SCALE Code Package and MultiGroup Cross Section Libraries for Analysis of LeadCooled 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 GEANT4Based Implementations 
Pia, Maria Grazia R&D for CoWorking Condensed and Discrete Transport Methods in GEANT4 Kernel 
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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 CoarseMesh Spectral Nodal Solution of SlabGeometry 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 RansBased CFD Simulations of Sodium Fast Reactor WireWrapped Pin Bundles 
Pointer, W. David MultiResolution 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 
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Ponomarev, Aleksandr S. Experimental and Computational Study on Profiling Heat Generation Fields in Modular HTGR with Annular Core Made on ASTRA Critical Facility 
PonomarevStepnoi, 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 CoolantVoid Reactivity in CANDU Generation III+ 
Popov, Alexi Ventzeslavov Achieving Negative CoolantVoid 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 BC523A CaptureGated 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 NonExtinction Probability for Prompt Critical Systems 
Prinja, Anil K. A Theoretical Result for MomentPreserving 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 RealTime 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 
PuenteEspel, 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 GEANT4Based Implementations 
Quintieri, Lina R&D for CoWorking 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. GalerkinQuadratures for the Sn Method in 2D Cartesian Geometries and Application to ForwardPeaked 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 PDEConstrained Optimization 
Ragusa, Jean C. Spatial Adaptivity for TimeDependent Diffusion Problems 
Ragusa, Jean C. GoalOriented Mesh Adaptivity for MultiDimension SPN Equations 
Ragusa, Jean C. A P1 Conforming DSA Scheme for DGFEM SN Transport 
Rahnema, Farzad A Simplified 2D HTTR Benchmark Problem 
Rahnema, Farzad 2Dimensional 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 NeuralBased Inversion of SpaceEnergy 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 LinearDiscontinuous CutCell Discretization for the Sn Equations in RZ Geometry 
Reitsma, Frederik A Comparison of Pebble Mixing and Depletion Algorithms Used in PebbleBed Reactor Equilibrium Cycle Simulation 
Rhodes III, Joel D. CASMO5 Versus MCNP5 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 PlateType Fuel Model to a MultiPhysics 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 IrregularShape Elements for NavierStokes Equations 
Ro, TaeIk Benchmark Experiment of Neutron Resonance Scattering Models in Monte Carlo Codes 
Roberts, Jeremy A. Adjoint CurrentBased Approaches to Prostate Brachytherapy Optimization 
Roblin, Philippe Improved Thermal Modeling of a SNF ShippingCask Drying 
Rohde, Ulrich Influence of the NeutronKinetic 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 CellWise BlockJacobi Splitting in TwoDimensional 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, JeanMichel HighOrder Discrete Ordinate Transport in NonConforming 2D Cartesian Meshes 
Russ, William R. Evaluation of Numerical Techniques for Optimization of ISOCS Modeled Detector Measurement Geometries 
Russkov, Alexander A. The CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
Russkov, Alexander A. Experience in the Use of the MonteCarlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations 
Ryzhikov, Gennady A. Modeling of Radiation Transport in Coupled AtmosphereSnowIceOcean 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 
SanchezEspinoza, V.H . Development of a Coupling Scheme between MCNP and COBRATF 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 2D Unstructured Meshes 
Saracco, Paolo R&D for CoWorking 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 TwoPhase Flows 
Schaefer, Jason P. Subspace MultiSCALE Approach for Reactor Analysis, Part I: Energy Variable 
Schillebeeckx, Peter Jose Calibration of the BC523A CaptureGated Liquid Scintillation Detector 
Schitthelm, Oliver MonteCarloBased 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 CoWorking 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 TimeDependent Anisotropic Distributed Source Capability in Transient 3D Transport Code TORTTD 
Seubert, Armin EnergyAngle Dependent Neutron Source in Deterministic Transport Codes with Spherical Harmonic Expansion 
Shaver, Mark MultiGroup Transport Methods for HighResolution Neutron Activation Analysis 
Shearer, Micheal Discrete Ordinate Mapping Algorithm for RegionBased 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 CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
Shrimpton, Paul C. Development of PC Based Monte Carlo Simulations for the Calculation of ScannerSpecific 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 RansBased CFD Simulations of Sodium Fast Reactor WireWrapped Pin Bundles 
Singh, Suneet Modified Choke Flow Criterion for the TwoPhase TwoFluid Model 
Sinitsa, Valentin Experience in the Use of the MonteCarlo 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 3D Sn Implemented in PENTRAN 
Sjoden, Glenn E. Transport Methods Used for Homeland Security and NonProliferation 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 OECDNEA 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 
SmedleyStevenson, Richard A NonLinear Optimal Discontinuous PetrovGalerkin Method for Stabilising the Solution of the Transport Equation 
SmedleyStevenson, Richard P. A Linear SIMC Scheme Suitable for Extension to MultiDimensions 
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 CADBased Geometries in Monte Carlo Radiation Transport 
Smith, Eric MultiGroup Transport Methods for HighResolution Neutron Activation Analysis 
Smith, Jeffrey RansBased CFD Simulations of Sodium Fast Reactor WireWrapped Pin Bundles 
Smith, Kord CASMO5 Versus MCNP5 Benchmark of Radial Power Profile in a Fuel Pin 
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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 
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Solomon Jr., Clell J. A Weighted Adjoint Source for WeightWindow Generation by Means of a Linear Tally Combination 
Sood, Avneet A Weighted Adjoint Source for WeightWindow Generation by Means of a Linear Tally Combination 
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Stamnes, Jakob Modeling of Radiation Transport in Coupled AtmosphereSnowIceOcean Systems 
Stamnes, Knut Modeling of Radiation Transport in Coupled AtmosphereSnowIceOcean Systems 
Stander, Gerhardt An Automated Cross Section Parameterization Method for MTR Application 
Sternat, Mathew Cross Section Inference Based on PDEConstrained Optimization 
Su, Bingjing Simulating Small Changes in System Response by MCNP5 
Sudhakar, Manju R&D for CoWorking Condensed and Discrete Transport Methods in GEANT4 Kernel 
Sugimura, Naoki Verification of the Resonance Calculation Model for Rod Cluster Control Based on UltraFineGroup 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 
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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 UltraFineGroup Spectrum Calculation in the AEGIS Code 
Taddeucci, Terry Improving the Nuclear Data Base for NonProliferation 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 I1 of the OECD LWR UAM Benchmark 
Tatsumi, Masahiro Verification of the Resonance Calculation Model for Rod Cluster Control Based on UltraFineGroup 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 CADBased Geometries in Monte Carlo Radiation Transport 
Taylor, J. Bryce A TimeDependent 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 CoolantVoid Reactivity in CANDU Generation III+ 
Thomas, Justin W. RansBased CFD Simulations of Sodium Fast Reactor WireWrapped Pin Bundles 
Thomas, Justin W. MultiResolution 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 VVER1000 Assembly and Core Benchmarks 
Tokuhiro, Akira T. RansBased CFD Simulations of Sodium Fast Reactor WireWrapped Pin Bundles 
Tomasevic, Djordje I. An Extension of the Multigroup Analytic Nodal Method (MANM) to Problems in HexagonalZ 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 NonProliferation and Homeland Security 
Trahan, Travis GalerkinQuadratures for the Sn Method in 2D Cartesian Geometries and Application to ForwardPeaked Scattering Particle Transport Problems 
Trama, JeanChristophe Pierre Importing CAD to TRIPOLI(R) 
Trumbull, Timothy Comparison of Some Monte Carlo Models for Bound Hydrogen Scattering 
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TsigeTamirat, Haileyesus Current Status of the CAD Interface Program McCad for MC Particle Transport Codes 
Tsofin, Vladimir I. Experience in the Use of the MonteCarlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations 
Tucker, Julie D. Determination of SoluteInterstitial Interactions in NiCr by First Principles 
Turcksin, Bruno Spatial Adaptivity for TimeDependent Diffusion Problems 
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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 NonProliferation 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 UltraFineGroup 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 2D PebbleBed 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 ATHLETQUABOX/CUBBOX 
Velkov, Kiril Uncertainty Analysis of COBRATF 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 TH3DNK 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 VVER1000 Assembly and Core Benchmarks 
Vlachoudis, Vasilis FLAIR: A Powerful but User Friendly Graphical Interface for FLUKA 
Voloschenko, Andrei M. The CNCSN2: One, Two and ThreeDimensional Coupled Neutral and Charged Particle Discrete Ordinates Code System 
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Wachspress, Eugene L. Generalized Finite Elements 
Wagner, John ForwardWeighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities 
Wagner, John Automated WeightWindow 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 CellWise BlockJacobi Splitting in TwoDimensional Geometry 
Warsa, James Negative Flux Fixups in Discontinuous Finite Element SN Transport 
Warsa, James S. TimeStep Limits for a Monte Carlo ComptonScattering 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 RegionBased Quadrature Sets 
Watson, Aaron M. Coupled Energy Group Iteration Scheme for Deterministic Transport Problems 
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Weidenspointner, Georg R&D for CoWorking 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 
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Weiss, FrankPeter Influence of the NeutronKinetic Feedback Parameter Variation on an Anticipated Transient without Scram in a PWR 
Wender, Stephen A. Improving the Nuclear Data Base for NonProliferation 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 PlateType Fuel Model to a MultiPhysics Code and Benchmark Modeling of Special Power Excursion Reactor Tests 
Williams, Mark An UltraFine 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 CADBased 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 CarloDeterministic Approach to Improve the Accuracy and Efficiency of Monte Carlo Calculations for Thermal Radiative Transfer 
Wollaber, Allan B. A Linear Stability Analysis for Nonlinear, 1D, Gray Implicit Monte Carlo Calculations 
Wollaber, Allan B. A TimeDependent Fleck Factor to Enhance the Accuracy of the Implicit Monte Carlo Equations 
Wollaber, Allan Recent Research Progress on UNIC at Argonne National Laboratory 
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Wroe, Andrew R&D for CoWorking Condensed and Discrete Transport Methods in GEANT4 Kernel 
Wu, Yican CADBased Modeling for 3D 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 
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Xu, Zhiwen CASMO5 Versus MCNP5 Benchmark of Radial Power Profile in a Fuel Pin 
Yamaji, Kazuya Hybrid Method of MOC and Sn Nodal for PWR Core Analysis 
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Yang, Jinan Application of the 'Functional Monte Carlo' Method to Estimate Continuous Energy kEigenvalues and Eigenfunctions 
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Yang, Won Sik Quasi Linear Representation of the Isotropic Scattering Source for the Method of Characteristics 
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Yesilyurt, Gokhan OntheFly Doppler Broadening for Monte Carlo Codes 
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Yi, Ce Hybrid Sn and RayTracing with Fictitious Quadrature for Simulation of SPECT 
Yi, Ce Accuracy of TITAN Based on a New OECDNEA Benchmark over a Range in Parameter Space 
Yi, Ce Automatically Tuned Adaptive Differencing Algorithm for 3D Sn Implemented in PENTRAN 
Yi, Ce Analysis and Benchmarking of PENTRAN Code using the OECDNEA Benchmark Problems 
Yoo, JaeWoon Benchmark Analysis of a Metallic Plutonium Fueled BFS551 Critical Assembly 
Yoo, JaeWoon 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 LooselyCoupled kEigenvalue Problem 
Zankl, Maria Development of PC Based Monte Carlo Simulations for the Calculation of ScannerSpecific Normalized Organ Doses from CT 
Zaritsky, Sergei M. Experience in the Use of the MonteCarlo Code Based Tracing Algorithm and the Volume Fraction Method in VVER Radiation Shielding Calculations 
Zeller, Michael Comparison of MCNP and WIMSAECL/RFSP Calculations against Critical Heavy Water Experiments in ZED2 with CANFLEXLVRF and CANFLEXLEU Fuels 
Zeng, Qin CADBased Modeling for 3D Particle Transport 
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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 
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Zhang, Juying Deformable and PostureChangeable Computational Phantoms and Dosimetry Data for Standard ExternalBeam 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 
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Zwermann, Winfried Influence of Nuclear Data Evaluations on Full Scale Reactor Core Calculations 

