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

Insepov, Z. Computer Simulation of Bubble Formation

Iwanaga, Kohei Treatments of TimeDerivatives of Neutron Kinetics Equation for SubCritical System with Neutron Source and Monte Carlo Calculation

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

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

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

Interpolation Methods and Splice Options for ThreeDimensional Transport Calculations Using Partisn

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

Jiminez, J. LWR MultiPhysics Developments and Applications Within the Framework of the NURESIM European Project

Johnson, Seth An Embedded SemiAnalytical Benchmark Via Iterative Interpolation for Neutron Transport Methods Verification

Joo, H. The MC21 Monte Carlo Transport Code

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

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

Joo, HyungKook VHTR Numerical Benchmark Based on the Compact Nuclear Power Source Experiments

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

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

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

Kaburaki, Hideo A ThreeDimensional MesoScale Modeling for Helium Bubble Growth in Metals

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

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

Kashaeva, E.A. Stochastic Geometry in PRIZMA Code

Kaushik, D. PNFE Component of the UNIC Code

UNIC: Ultimate Neutronic Investigation Code

Software Design of SHARP

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

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

Keresztúri, A. Experience in Simulation of Startup Measurements in the VVER440 Reactor Using the KIKO3D Code

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

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

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

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

Comparison of TwoStep Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR400 Problem

Kim, T. K. Neutronics Assessment of Stringer Fuel Assembly Designs for the LiquidSaltCooled Very High Temperature Reactor (LSVHTR)

Kim, Yonghee Monte Carlo Equilibrium Cycle Analysis of a DeepBurn MHR Core Charged with KernelBased TRISO Fuel

Kitamura, Yasunori Performance of the Diffusion and Simplified PN Theories for BWR PinbyPin Fine Mesh Core Analyses

Joint Moments of Neutron Number and Medium State in a TimeVarying Multiplying Medium

Klaver, P. Stability of Uncommon Interstitials in Fe

Stability and Mobility of SelfInterstitial Atoms and their Clusters in FeCr Alloys: An AtomicLevel Study

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

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

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

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

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

Koga, James Computational Physics of Photon Science

High Power Gamma Ray Source by Radiation Damping

Kosheleva, E. V. Materials in Extreme Conditions the Critical Phenomena and Phase Transfer in the Dynamic Destruction

The Universal Properties of Metals Behavior in the Dynamic Destruction Phenomenon in a Wide Range of Longevity Under the Influence of HighPower Pulses of Radiation

Kramer, Kevin Osiris: A Modern, HighPerformance, Coupled, MultiPhysics Code For Nuclear Reactor Core Analysis

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

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

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

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

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

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

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

A Generalized Boltzmann Equation for "NonClassical" Particle Transport

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

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

A MultiScale Approach for the Neutronic Kinetics Equations Using the Mixed Dual Solver MINOS

Domain Decomposition Methods for Core Calculations Using the MINOS Solver

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

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

Le Potier, Christophe Radionuclide Transport Calculations from HighLevel LongLived Radioactive Waste Disposal in Deep Clayed Geologic Formation Toward Adjacent Aquifers

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

Leclere, M. UNIC: Ultimate Neutronic Investigation Code

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

Lee, Hyun Chul Comparison of TwoStep Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR400 Problem

Lee, John C. Degradation Monitoring in IRIS Steam Generators

Lee, YoungSeok Doppler Coefficient of Reactivity  Benchmark Calculations for Different Enrichments of UO2

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

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

UNIC: Ultimate Neutronic Investigation Code

A New Paradigm for Whole Core Neutron Transport Without Homogenization

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

Lo, Simon Eulerian TwoPhase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis

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

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

Lou, Tak Pui Simulation of Cargo Container Interrogation by DD Neutrons

Lowrie, Robert B. Shock Wave Solutions for Radiation Hydrodynamics

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

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

Mahadevan, Vijay Application of HighOrder Implicit Schemes for Nonlinear MultiPhysics Simulations

Maiorino, J.R. Analytical Benchmarks for the Kinetics of AcceleratorDriven Systems

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

Malerba, L. Stability of Uncommon Interstitials in Fe

Stability and Mobility of SelfInterstitial Atoms and their Clusters in FeCr Alloys: An AtomicLevel Study

Malyshkin, G.N. Stochastic Geometry in PRIZMA Code

Maráczy, Cs. Experience in Simulation of Startup Measurements in the VVER440 Reactor Using the KIKO3D Code

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

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

MartindelCampo, C. Optimization Procedure for Radial BWR Fuel Lattice Design Using Genetic Algorithms

LPPF Prediction in a BWR Fuel Lattice Using Artificial Neural Networks

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

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

Matthews, Kirk Matrix Albedo for Discrete Ordinates InfiniteMedium Boundary Condition

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

A P1 Benchmark for Time Dependent Thermal Radiative Transfer

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Morel, Jim E. Subcell S_{N} Sweeping for Meshes with Reentrant Cells

Solution Algorithms for a P_{N1}Equivalent S_{N} Angular Discretization of the Transport Equation in OneDimensional Spherical Coordinates

A FokkerPlanck Method for Modeling Compton Scattering in Implicit Monte Carlo Simulations

Mori, Takamasa Treatments of TimeDerivatives of Neutron Kinetics Equation for SubCritical System with Neutron Source and Monte Carlo Calculation

Morrow, R. E. A keff Search Capability in MC21

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

ENDF/BV, ENDF/BVI, and ENDF/BVII.0 Results for the DopplerDefect Benchmark

ENDF/BVII.0, ENDF/BVI, JEFF3.1, and JENDL3.3 Results for Unreflected Plutonium Solutions and MOX Lattices

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

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

Mukhamadiev, R. F. Stochastic Geometry in PRIZMA Code

Nachaoui, A. A MultiScale Approach for the Neutronic Kinetics Equations Using the Mixed Dual Solver MINOS

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

Nazaryan, Vahagn Comparison of Different Shielding Materials Used at Proton Accelerators and CostBenefit Analysis

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

Convergence Testing for MCNP5 Monte Carlo Eigenvalue Calculations

Neda, Monika Stochastic FiniteElement Approximation of the Parametric Dependence of Eigenvalue Problem Solution

Nevinitsa, V.A. Reconstruction of the Local NeutronPhysical Functionals in Surface Harmonics Method

Nicolino, C. Reactivity Oscillations in Molten Salt Reactors

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

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

Noh, Jae Man Comparison of TwoStep Diffusion Solutions and Monte Carlo Solutions to a Doubly Heterogeneous PBMR400 Problem

Norman, G. Computer Simulation of Bubble Formation

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

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

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

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

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

Okuda, Hiroshi Uncertainty Analysis of Multiple Canister Repository Model by LargeScale Calculation

Olsson, P. Stability and Mobility of SelfInterstitial Atoms and their Clusters in FeCr Alloys: An AtomicLevel Study

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

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

Otobe, Tomohito Computational Physics of Photon Science

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

Earthquakes and Pebble Bed Reactors: TimeDependent Densification

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

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

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

Palmiotti, G. PNFE Component of the UNIC Code

UNIC: Ultimate Neutronic Investigation Code

A New Paradigm for Whole Core Neutron Transport Without Homogenization

Software Design of SHARP

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

Stochastic FiniteElement Approximation of the Parametric Dependence of Eigenvalue Problem Solution

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

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

Park, Hyeong Kae Verification of the Coupled SpaceAngle Adaptivity Algorithm for the Finite ElementSpherical Harmonics Method Via the Method of Manufactured Solutions

Parsons, Dennis Osiris: A Modern, HighPerformance, Coupled, MultiPhysics Code For Nuclear Reactor Core Analysis

Pattnaik, Aliva Load Balancing Strategy for Radiation Transport Code EVENT

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

Pázsit, I. Investigation of the Validity of the PointKinetic Approximation and of the BreakFrequency Method in 2D Subcritical Systems

Monte Carlo Models of Neutron Detection with Organic Scintillators

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

Joint Moments of Neutron Number and Medium State in a TimeVarying Multiplying Medium

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

Peterson, P.F. The MultiPhysics UserFriendly GasDynamics Code Visual Tsunami 2.0

Picca, P. Analytical Benchmarks for the Kinetics of AcceleratorDriven Systems

Platonova, L.A. The Universal Properties of Metals Behavior in the Dynamic Destruction Phenomenon in a Wide Range of Longevity Under the Influence of HighPower Pulses of Radiation

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

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

Eulerian TwoPhase Computational Fluid Dynamics for Boiling Water Reactor Core Analysis

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

Pounders, Justin FluxLimited Diffusion Coefficients in Reactor Physics Applications

Poveschenko, Tamara MultiGroup Nondiffusion NeutronPhysical Characteristics of the Nuclear Reactor Cell with Axial Symmetry

Pozzi, S. PulseShape Discrimination for Identification of Neutron Sources Using the BC501A Liquid Scintillator

A Sequential Least Squares Algorithm for Neutron Spectrum Unfolding from PulseHeight Distributions Measured with Liquid Scintillators

Photonuclear Physics Models, Simulations and Experiments for Nuclear Nonproliferation

Monte Carlo Models of Neutron Detection with Organic Scintillators

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

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

Prinja, Anil K. A New Electron EnergyLoss Straggling Algorithm in MCNP

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

Subcell S_{N} Sweeping for Meshes with Reentrant Cells

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

Stochastic Averaging of Cross Section Uncertainty in Transport

Prinsloo, Rian CrossSection Parameterization Using QuasiRegression Approach

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

Procassini, Richard Osiris: A Modern, HighPerformance, Coupled, MultiPhysics Code For Nuclear Reactor Core Analysis

A Monte Carlo Method for Calculating Initiation Probability

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

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

Punin, V.T. Materials in Extreme Conditions the Critical Phenomena and Phase Transfer in the Dynamic Destruction

The Universal Properties of Metals Behavior in the Dynamic Destruction Phenomenon in a Wide Range of Longevity Under the Influence of HighPower Pulses of Radiation

