M&C 2019

Author Index

Full Issue

Arbitrary-Order Discontinuous Galerkin Discretization for SN Transport Using Polygonal Bernstein-Bézier Functions

Michael W. Hackemack (NNL)

High Order Mixed Finite Element Discretization for the Variable Eddington Factor Equations

Samuel S. Olivier (U. C., Berkeley), Peter G. Maginot (LANL), Terry S. Haut (LLNL)

Extension of the Discrete-Ordinates Transport Solver IDT to Regular Two-Dimensional Triangular Meshes

G. F. Nallo (Politecnico di Torino), E. Masiello, J.-J. Lautard (CEA), P. Ravetto (Politecnico di Torino)

Quadrature Lumping the DFEM SN Equations in x-y Geometry

Peter G. Maginot (LANL), Terry S. Haut (LLNL)

The Quasidiffusion Method for Transport Problems on Adaptive-Like Arbitrary Quadrilateral Meshes in 2D r-z Geometry

Jesse P. Jones, Dmitriy Y. Anistratov (NCSU), Jim E. Morel (Texas A&M)

Scalable Angular Adaptivity and Robust Error Metrics

S. Dargaville (Imperial College London), A. G. Buchan (Queen Mary Univ.) R. P. Smedley-Stevenson (AWE), P. N. Smith (Wood PLC), C. C. Pain (Imperial College London)

Solving the SN Transport Equation Using High Order LAX- Friedrichs WENO Fast Sweeping Methods

Dean Wang, Tseelmaa Byambaakhuu (Ohio State), Sebastian Schunert (INL), Zeyun Wu (Virgina Commonwealth)

Batched Monte Carlo and the Confidence Interval

Jason D. Haverkamp (NNL)

Global Variance Reduction Scheme with Self-Adaptive Weight-Window Mesh in the Serpent 2 Monte Carlo Code

Jaakko Leppänen, Mika Jokipii (VTT)

Development of A New Weight Window Generator Based on Markov Decision Process

Peng Zhang, Hyunsuk Lee, Mai Nguyen Trong Nhan, Matthieu Lemaire, Deokjung Lee (UNIST)

On the use of Different Variance Reduction Techniques Within MCNP to Calculate the Flux on the Concrete Walls of a Pressurized Water Reactor

Mariya Brovchenko, Léa Tillard (IRSN), Kenneth W. Burn (ENEA), Bertrand Cochet, Alexis Jinaphanh (IRSN)

Real Variance Estimation of Local Tallies Using Spectral Analysis Method in p-CMFD assisted Monte Carlo Criticality Calculation,

HyeonTae Kim (KAIST), YuGwon Jo (KHNP), Yonghee Kim (KAIST)

Variance-Reduction Methods for Monte Carlo Kinetic Simulations

Margaux Faucher, Davide Mancusi, Andrea Zoia (CEA, Saclay)

Calculating the Covariance Matrix of a Neutron Spectrum in the High Flux Reactor

N. L. Asquith, S. C. van der Marck (NRG)

Continuous Energy Monte Carlo Criticality Calculation of Random Media Under Power Law Spectrum

Taro Ueki (JAEA)

Detailed Analysis of the Asymptotic Convergence of the Angular Discretization Error in the Uncollided Solution to the Discrete Ordinates Transport Equation

Xiaoyu Hu, Yousry Y. Azmy (NCSU)

Deterministic Transport Solution of Multiplicity Counting Equations

Philippe Humbert (CEA)

Photonuclear Reactions in SERPENT 2 MONTE CARLO Code

Toni Kaltiaisenaho (VTT)

PyNE Sub-Voxel R2S for Shutdown Dose Rate Analysis

Xiaokang Zhang (IPP, Chinese Academy of Sciences), Patrick C. Shriwise (U. W., Madison), Songlin Liu (Univ. Sci & Technol.), Paul P. H. Wilson (U. W., Madison)

Photon Polarization and Doppler Broadening in Low Energy Monte Carlo Transport

Edmund Caro (NNL)

A Stochastic Theory of Deposited Fission Energy in Neutron Chains

Anil K. Prinja, Patrick O'Rourke (Univ. New Mexico)

A Fully Monte Carlo Solution of the Thermal Radiative Transfer Equations with Compton Scattering

Simon R. Bolding, Alex R. Long (LANL), Kyle A. Beyer (Univ. Michigan), Kendra P. Long (LANL)

Non-Equilibrium Radiative Transfer Solutions Using a Two-Group Diffusion Model

Ryan G. McClarren (Notre Dame)

Towards Asymptotic Diffusion Limit Preserving High-Order, Low-Order Method

H. Park (LANL)

Multilevel Methods with Multigrid in Energy for Thermal Radiative Transfer Problems

Dmitriy Y. Anistratov (NCSU)

A Reduced-Order Model for Thermal Radiative Transfer Problems Based on Multilevel Quasidiffusion Method

Joseph Coale, Dmitriy Y. Anistratov (NCSU)

Linear-Multifrequency-Grey Acceleration for Thermal Radiation Transport in the Presence of Compton Scattering

A. T. Till (LANL), J. E. Morel (Texas A&M)

Design of a Deep Learning Surrogate Model for the Prediction of FHR Design Parameters

A. J. Whyte, Z. Xing, G. T. Parks, E. Shwageraus (Cambridge)

A Study of the Bethe and Placzek Approximations

Guilherme Guedes (Centro Federal de Educação Tecnológica Celso Suckow da Fonseca), Daniel A. P. Palma (Brazilian Nuclear Energy Commission), Amir Z. Mesquita (Centro de Desenvolvimento de Energia Nuclear (CDTN)), Alessandro da C. Gonçalves (Programa de Engenharia Nuclear - PEN/C)

Development of a Spatially-Dependent Resonance Self-Shielding Method in CASMO5

Rodolfo Ferrer, Joshua Hykes (Studsvik Scandpower)

The New Neutron Noise Solver of the Monte Carlo Code TRIPOLI-4®

Amélie Rouchon, Walid Jarrah, Andrea Zoia (CEAQ)

Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs

Andrei Rykhlevskii (Univ. Illinois), Benjamin R. Betzler, Andrew Worrall (ORNL), Kathryn Huff (Univ. Illinois)

Hierarchical CMFD Preconditioning in Space and Energy

Michael W. Hackemack, Troy L. Becker (NNL)

Spatial Discretization Error Reduction in Axial MOC Solver of Three-Dimensional Heterogeneous Transport Calculation Code GALAXY-Z

Koichi Ieyama, Kazuya Yamaji, Hiroki Koike, Daisuke Sato (Mitsubishi Heavy Industries)

Fully-Implicit, High-Order, Reconstructed Discontinuous Galerkin Method for Supercritical Fluid Flows

R. Barney (U. C., Davis), R. Nourgaliev (LLNL), J.-P. Delplanque (U.C., Davis), R. McCallen (LLNL)

Non-Linear Eddy Viscosity Models for Modeling the Turbulent Phenomena in Molten Salt Reactors

M. Tano (Texas A&M), P. Rubiolo (Grenoble Inst. Technol.), J. Ragusa (Texas A&M)

Multiscale Core Thermal-Hydraulics Analysis of the Pebble Bed Fluoride-Salt-Cooled High-Temperature Reactor

A. J. Novak, R. N. Slaybaugh (U. C., Berkeley), R. C. Martineau (INL)

Steady-State Thermal-Hydraulic Analysis of Fluoride Salt-Cooled Small Modular Advanced High-Temperature Reactor (SmAHTR)

Sriram Chandrasekaran, Srinivas Garimella (Georgia Tech)

Demonstration of a Coupled Simulation for Modelling Primary Pump Coastdown Transient for MSRE

Qi Chen, Krishna Podila, Yanfei Rao, Xianmin Huang, Peter Pfeiffer (CNL)

Direct Numerical Simulations of Turbulence in Molten Salts Coolants

M. Tano (Texas A&M), P. Rubiolo (Grenoble Inst. Techol.), J. Ragusa (Texas A&M)

Neutron Noise Simulations in a Heterogeneous System: A Comparison Between a Diffusion-Based and a Discrete Ordinates Solver

A. Mylonakis, H. Yi, P. Vinai, C. Demaziere (Chalmers Univ.)

Highly Uniform Quadrature Sets for the Discrete Ordinates Method

Thomas Camminady, Martin Frank, Jonas Kusch (KIT)

Ray-Effect Mitigation for the Discrete Ordinates Method Using Artificial Scattering

Thomas Camminady, Martin Frank (KIT), Cory D. Hauck (ORNL), Jonas Kusch (KIT)

Three-Dimensional Core Shielding Benchmark Using AETIUS and DORT Codes

Jong Woon Kim, Jae Hoon Song, Seongho Song, Jin Young Cho (KAERI)

Improving the Performance of Transport Sweeps with Thermal Upscattering Acceleration at Massively Parallel Scale

Milan Hanuš, Jean Ragusa (Texas A&M)

APR-1400 Whole-Core Depletion Analysis with MCS

Tung Dong Cao Nguyen, Hyunsuk Lee, Jiwon Choe, Matthieu Lemaire, Deokjung Lee (UNIST)

MONK11A: Status and Plans for the MONK Monte Carlo Code for Criticality Safety and Reactor Physics Analyses

Simon Richards, Geoff Dobson, David Hanlon, Ray Perry, Francesco Tantillo, Tim Ware (Wood)

Pre-Collapsed Fluorescence Methodology for Monte Carlo Radiation Transport Simulations

Jason T. Thompson, David P. Griesheimer, Edmund Caro (NNL)

Preliminary CEFR Analysis by Monte Carlo Codes

Tuan Quoc Tran, Jiwon Choe, Xianan Du, Alexey Cherezov, Hyunsuk Lee, Deokjung Lee (UNIST)

The Use of MCNP 6.2 KCODE for High Fidelity Near Critical Benchmarks

Daniel Timmons (Univ. New Mexico, LANL), Michael Rising (LANL), Chrisopher Perfetti (Univ. New Mexico)

Solver Recommendation for Transport Problems in Slabs Using Machine Learning

Jinzhao Chen, Japan K. Patel, Richard Vasques (Ohio State)

A Case Study on the Use of Adjoint Particle Transport in Computationally Intensive Regions of a Transport Problem, Conducted on a Passive Gamma Emission Tomography Geometry

Dylan S. Hoagland (NCSU), Rick S. Wittman, Erin A. Miller (PNNL)

DRF Methodology for Reactor Pressure Vessel Dosimetry

Meng-Jen Wang, Alireza Haghighat (Virginia Tech)

A New Implicit Monte Carlo Thermal Photon Transport Capability Developed Using Shared Monte Carlo Infrastructure

Patrick S. Brantley, N. A. Gentile, Michael A. Lambert, M. Scott McKinley, Matthew J. O'Brien, Jonathan A. Walsh (LLNL)

Application of the SuPer-Homogenization Method in Fast Reactor Analysis System SARAX

Linfang Wei, Youqi Zheng, Bowen Xiao, Longfei Xu, Hongchun Wu (Xi'an Jiaotong Univ.)

Validation of Coupled Neutron-Photon Transport Mode of Monte Carlo Code MCS

Matthieu Lemaire, Fathurrahman Setiawan, Hyunsuk Lee, Peng Zhang, Deokjung Lee (UNIST)

Self-Shielding in PARTISN

Thomas G. Saller (LANL)

POLARIS-CASMO Verification with Burn-Up Dependence and NEMTAB Library Generation with Uncertainties

Antonella Labarile, Rafael Miró, Gumersindo Verdú (Univ. Politècnica de València)

Development of Generalized Response Sensitivity Analysis Capability in RMC Code

Guanlin Shi, Conglong Jia, Quan Cheng, Kan Wang (Tsinghua Univ)

Sensitivity and Uncertainty Analysis Capability in MCS for UAM Benchmark

Yunki Jo, Chidong Kong, Alexey Cherezov, Deokjung Lee (UNIST)

A Comparison Between Time Domain and Frequency Domain Calculations of Stationary Neutron Fluctuations

M. Viebach, C. Lange (TU Dresden), S. Kliem (Helmholtz-Zentrum Dresden - Rossendorf), C. Demaziere (Chalmers Univ.), U. Rohde (HZDR-Innovation Rossendorf), D. Hennig (TU Dresden), A. Hurtado (TU Dresden)

STRIGA: A Computer Tool for TRIGA Reactor Burnup Calculations

Anže Punger?i?, Dušan ?ali?, Luka Snoj (Jožef Stefan Inst.)

SERPENT-Tools: A Python Package for Expediting Analysis with SERPENT Data

A. Johnson, D. Kotlyar (Georgia Tech)

Gamma Scan Validation of the ARTEMIS BWR Models

Nicolas Martin, Alex Bennett, Michael Riedmann (Framatome)

Calculation of DPA in the Main Components of a LBE-Cooled Fast Reactor (BLESS-D)

Eing Yee Yeoh, Linsen Li, Xiaosong Chen, Yaodong Chen (State Power Investment Corporation)

Verification of Asymmetric Fuel Assembly Treatment in STREAM/RAST-K 2.0

Jiwon Choe, Sooyoung Choi, Jinsu Park, Hyunsuk Lee, Matthieu Lemaire (UNIST), Ho Cheol Shin, Hwan-Soo Lee (KHNP), Deokjung Lee (UNIST)

Activities of the OECD Nuclear Energy Agency Data Bank Computer Program Services

Alice Dufresne, Elena Poplavskaia, Kenya Suyama (OECD)

A Collaborative Virtual Reality System (VRS) with X3D Visualization for RAPID

Valerio Mascolino, Alireza Haghighat, Nicholas Polys, Meng-Jen Wang, Srijith Rajamohan (Virginia Tech)

Assessment of nTRACER and PARCS Performance for VVER Configurations

Marianna Papadionysiou (PSI), Kim Seongchan (Seoul Nat’l Univ.), Mathieu Hursin, Alexander Vasiliev, Hakim Ferroukhi, Andreas Pautz (PSI), Han Gyu Joo (Seoul Nat’l Univ.)

Energy-Dependent Fission Yields in Advanced Reactors

Toni Kunchev, Eugene Shwageraus (Cambridge), Jaakko Leppänen (VTT)

Preliminary Results for OPR1000/APR1400 Whole-Core Analysis with Neutron Transport Code Stream

Sooyoung Choi, Deokjung Lee (UNIST)

Preliminary Results of BEAVRS Whole-Core Multi-Cycle Analysis with Neutron Transport Code Stream

Sooyoung Choi, Deokjung Lee (UNIST)

PARAGON2 Validation Using High Enriched Evaluated Criticality Benchmark Experiments

Austin Carter, Mohamed Ouisloumen (Westinghouse)

Implementation of Gamma Transport Capability in MPACT

Xinyan Wang, Yuxuan Liu, William Martin (Univ. Michigan), Shane Stimpson (ORNL)

Validation of Nuclide Depletion Capabilities in Monte Carlo Code MCS using Spent Fuel Isotopic Measurements

Bamidele Ebiwonjumi, Hyunsuk Lee, Wonkyeong Kim, Sooyoung Choi, Deokjung Lee (UNIST)

Westinghouse 2-Loop Plant Loading Pattern Optimization for Last Few Cycles Before Shutdown

Jaerim Jang, Jiwon Choe, Sooyoung Choi, Jinsu Park, Matthieu Lemaire, Deokjung Lee (UNIST), Ho Cheol Shin (KHNP)

Assessing the Performance of Functional Expansion Tallies in the Serpent 2 Monte Carlo Code

Heikki Suikkanen, Ville Rintala (LUT Univ.)

Kraken—An Upcoming Finnish Reactor Analysis Framework

Ville Valtavirta, Ville Hovi, Henri Loukusa, Antti Rintala, Ville Sahlberg, Riku Tuominen, Jaakko Leppänen (VTT)

Multi-Cycle Analysis of OPR1000 Using Multi-Physics Coupled Codes of RAST-K, CTF and FRAPCON

Hanjoo Kim, Alexey Cherezov (UNIST), Jiankai Yu (MIT), Jinsu Park, Deokjung Lee (UNIST)

Improved Source Treatment for the Three-Temperature Implicit Monte Carlo Equations

M. Cleveland, R. Rauenzahn (LANL)

A Quadratic Programming Based Flux Fixup Method for Arbitrarily High-Order Discontinuous Galerkin Discretizations of the SN Transport Equations

Ben C. Yee, Terry S. Haut, Vladmir Z. Tomov (LLNL), Peter G. Maginot (LANL)

Linear Short Characteristics Applied to 3D Heterogeneous Cartesian Cells for Transport-Based Core Simulations

Emiliano Masiello, Roland Lenain, Ford Wesley (CEA)

Improved Quasi-Static Method for Multi-Scheme Neutron Transport with Finite Element Methods

Yaqi Wang, Vincent M. Laboure, Sebastian Schunert, Mark DeHart, Richard C. Martineau (INL)

Reduced-Order Modeling of Neutron Transport Separated in Space and Angle via Proper Generalized Decomposition

Kurt A. Dominesey, Wei Ji (RPI)

Uncollided-Flux Treatment in Arbitrary Polyhedral Grids

Milan Hanuš, Logan H. Harbour, Jean Ragusa, Michael P. Adams, Marvin L. Adams (Texas A&M)

Fourier Analysis of Inexact Parallel Block Jacobi with Source Iteration Preconditioning and Computational Experimentation with Parallel Block Jacobi / Source Iteration Hybrid Methods

Dylan S. Hoagland, Yousry Y. Azmy (NCSU)

1D Transport Using Neural Nets, SN, and MC

Michael M. Pozulp (LLNL)

Simplified Method for Estimating the Effective Delayed Neutron Fraction with Monte Carlo Correlated Sampling

David P. Griesheimer, Nathan A. Gibson (Naval Nuclear Laboratory)

Discrete Ordinates Prediction of the Forced-Collision Variance Reduction Technique in Slab Geometry

Brian C. Kiedrowski (Univ. Michigan), Joel A. Kulesza, Clell J. Solomon (LANL)

Progress in the Validation of MCShield Code

Ruiyao Ma (Tsinghua Univ.), Zhen Wu, Li Ren (Tsinghua Univ., NUCTECH), Shenshen Gao, Rui Qiu, Chunyan Li, Wei Lu, Hui Zhang, Junli Li (Tsinghua Univ.)

Efficient Dynamic Threadsafe Neighbor Lists for Monte Carlo Ray Tracing

Sterling Harper (MIT), Paul Romano (ANL), Benoit Forget, Kord Smith (MIT)

Hybrid Tallies to Improve Performance in Depletion Monte Carlo Simulations

Jose L. Salcedo-Perez, Benoit Forget, Kord Smith, (MIT) Paul K. Romano (ANL)

Analysis of Fission Source Stationarity for a 3-D SMR Core Using Functional Expansion Tallies

Shikhar Kumar, Benoit Forget, Kord Smith (MIT)

Stabilizing the K-Alpha Iteration Algorithm in Very Subcritical Regimes

Colin Josey, Forrest B. Brown (LANL)

A Low-Rank Method for Time-Dependent Transport Calculations

Zhuogang Peng, Ryan G. McClarren (Notre Dame), Martin Frank (KIT)

Stability Characteristics of Multilevel Deterministic k-Eigenvalue Simulations

Kendra P. Long (LANL)

Theoretical Convergence Rate Analysis of a Unified CMFD Formulation with Various Diffusion Coefficients

Brendan Kochunas (Univ. Michigan)

Accuracy of the Reactor Core Simulations for Determination of the Antineutrino Spectrum for the SoLid Experiment at BR2 Reactor

Silva Kalcheva, Geert Van den Branden (SCK/CEN), Lydie Giot, Muriel Fallot (SUBATECH, IMT Atlantique)

Towards a Multiphysics Model for Tumor Response to Combined-Hyperthermia-Radiotherapy Treatment

Japan K. Patel, Richard Vasques (Ohio State), Barry D. Ganapol (Univ. Arizona)

Neutron Kinetics Equations in APOLLO3® Code for Application to Noise Problems

A. Gammicchia, S. Santandrea, I. Zmijarevic, Z. Stankovski (CEA), S. Dulla (Politecnico di Torino)

Identifying Sources of Bias from Nuclear Data in MCNP6 Calculations Using Machine Learning Algorithms

Pavel A. Grechanuk (Oregon State), Michael E. Rising (LANL), Todd S. Palmer (Oregon State)

An Exact Mathematical Multipole Representation of the Microscopic Cross-Sections for the Multi-Level Breit-Wigner and Reich-Moore Formalisms

Thomas Freiman, Mireille Coste-Delclaux, Francois-Xavier Hugot (CEA)

Interrogation and Analysis of Complex Fusion Decay Heat Benchmark Simulations

Mark Gilbert (UKAEA), Jean-Christophe Sublet (IAEA)

Expanded COG Criticality Validation Suite

David P. Heinrichs, Soon S. Kim (LLNL)

Determination of Extensive Set Dosimetric Reaction Rates for Testing of the Neutron Spectrum Unfolding Codes

E. Losa, M. Koš?ál, T. Czakoj, F. Brijar, V. Ju?í?ek, V. Rypar (Research Centre ?ež)

Data Fusion Techniques for Improving Fission Neutron Multiplicity Data

Benjamin Whewell, Ryan G. McClarren (Notre Dame), Simon Bolding (LANL)

A Resonance Calculation Method Using Energy Expansion Bases Based on a Reduced Order Model

Akio Yamamoto, Tomohiro Endo (Nagoya Univ.), Satoshi Takeda (Osaka Univ.), Hiroki Koike, Kazuya Yamaji, Koichi Ieyama, Daisuke Sato (Mitsubishi Heavy Industries)

Improved Formulation of the Method of Characteristics with Linear Source for 2D/1D and Multiphysics Calculations

Andrew P. Fitzgerald, Brendan Kochunas, Thomas Downar (Univ. Michigan)

Verification of Adjoint Functions of Natural Mode Equation by Generalized Iterated Fission Probability Method and by Analog Monte Carlo

Yasushi Nauchi (CRIEPI), Alexis Jinaphanh, Andrea Zoia (CEA)

Prediction of Spatial Flux Through Depletion

A. Johnson, D. Kotlyar (Georgia Tech)

Assessment of the Neutron Noise Induced by Stationary Fuel Assembly Vibrations in a Light Water Reactor

V. Verma (PSI), C. Demazière, P. Vinai (Chalmers Univ.), G. Ricciardi, R.. Jacqmin (CEA)

Analysis of Alpha Modes in Multigroup Transport

Richard Sanchez, Daniele Tomatis (CEA)

Development of Simplified Methods for Ex-Core Detector Response in MPACT

Yuxuan Liu (Univ of Michigan)

Stability Diagnosis of High-Fidelity Transport-Depletion Problems with Monte Carlo Perturbation Theory

P. Cosgrove, E. Shwageraus, G. T. Parks (Univ. of Cambridge)

MCNP and CFD Modeling of a Sodium Fast Reactor Sub-Assembly Channel to Capture Localized Temperature Peaking

A. Abou-Jaoude, S.-J. Yoon, S. E. Bays (INL)

Neutronic Simulation of Fuel Assembly Vibrations in a Nuclear Reactor

A. Vidal-Ferràndiz, A. Carreño, D. Ginestar (Univ. Politècnica de València), C. Demazière (Chalmers Univ.), G. Verdu (Univ. Politècnica de València)

Validation of an Advanced APOLLO3® Deterministic Scheme for Characterizing of the Jules Horowitz Irradiation Reactor Core

Matthieu Lebreton, Julien Politello, Gerald Rimpault, Jean-François Vidal (CEA)

Whole-Core Validation of the Superphénix Reactor Using WIMS11 and an Investigation into a Hybrid RZ-HEX SP3 Calculation Route

Una Davies (Cambridge), Ben Lindley, Brendan Tollit (Wood), Eugene Shwageraus (Cambridge)

Two-Level Multigrid Preconditioning of a Neutron Noise Diffusion Solver

Antonios Mylonakis, Paolo Vinai, Christophe Demaziere (Chalmers Univ.)

Upgrade of APOLLO3® Inner Thermohydraulic Feedback Model with THEDI, and Application to a Control-Rod Ejection Accident

Cyril Patricot, Roland Lenain, Dominic Caron (CEA)

SERPENT-Based Few-Group Cross Section Data for NESTLE-C

A. Trottier, S. Pfeiffer (CNL), D. Serghiuta (Canadian Nucl. Safety Comm.)

Comparison of Meshless and High-Order Polynomial Functions for Neutron Transport with Streamline-Upwind Petrov-Galerkin Stabilization

Brody Bassett (LLNL), Brian C. Kiedrowski (Univ. of Michigan)

Estimation of Energy Multigroup Neutron Source Distribution for Driving a Subcritical System at a Prescribed Power Density Level

Leonardo R. C. Moraes, Hermes A. Filho, Ricardo C. Barros (Univ. do Estado do Rio de Janiero)

Nodal Integral Method for Arbitrary Hexahedral Elements Applied to 3D Convection-Diffusion Equation

Ibrahim Jarrah, Rizwan Uddin (Univ. Illinois)

Rigorous Derivation for P2 Anisotropic Scattering Source For Hexagonal Core Analysis

Jin Young Cho, Kyunghoon Hoon Lee (KAERI)

Spatial Domain Decomposition for Transport Problems with Two-Level Acceleration Algorithms

Dmitriy Y. Anistratov (NCSU), James S. Warsa, Robert B. Lowrie (LANL)

Separated Representation of Spatial Dimensions in SN Neutron Transport Using the Proper Generalized Decomposition

Zachary M. Prince, Jean C. Ragusa (Texas A&M)

Sweep-Free Deterministic Transport

Richard P. Smedley-Stevenson (AWE)

Automated Acceleration and Convergence Testing for Monte Carlo Criticality Calculations

Forrest Brown, Colin Josey (LANL), Shawn Henderson (SNL), William Martin (Univ. Michigan)

Geometry and Performance Improvement of P++ Single Event Proton Scattering Algorithms on GPUs

Kristofer Zieb (LLNL), X. George Xu (RPI)

Experimental and Computational Benchmarking of RAPID Using the JSI TRIGA Mark-II Reactor

Valerio Mascolino (Virginia Tech), Anže Punger?i? (Jozef Stefan Inst.), Alireza Haghighat (Virginia Tech), Luka Snoj (Jozef Stefan Inst)

Validation of the Transient Fission Matrix Code tRAPID Against the Flattop-Pu Benchmark

Valerio Mascolino, Alireza Haghighat (Virginia Tech)

Study of the Interaction of Regions with Multi-Group and Continuous Energy Representation in Monte Carlo Calculations

Mikolaj Adam Kowalski, Eugene Shwageraus (Cambridge)

Fission Matrix Methods for Nuclear Thermal Propulsion Applications

Adam Rau, William Walters (Penn State)

?-Weighted Transition Rate Matrix Method

Ilham Variansyah (Univ. Michigan), Benjamin R. Betzler (ORNL), William Martin (Univ. Michigan)

Simulation of BEAVRS Cycle 2 with MCS Based Multi-Physics Coupling Code

Jiankai Yu (MIT), Alexey Cherezov, Hyunsuk Lee, Hanjoo Kim, Peng Zhang (UNIST), Benoit Forget (MIT), Deokjung Lee (UNIST)

Integration of the MONK Monte Carlo Neutronics Code in the NURESIM Platform

F. Tantillo, S. D. Richards, A. J. Smethurst, D. J. Long (ANSWERS)

Investigations into Coupling the MC21 Monte Carlo Transport Code to the CFX Computational Fluid Dynamics Code

Kyle E. Remley, David P. Griesheimer, Kevin J. Hogan, John R. Buchanan (NNL)

High Fidelity Multiphysics Strategies with Proteus and Nek5000 for Fast Reactor Applications

Emily R. Shemon, Yiqi Yu, Taek Kyum Kim (ANL)

Development of an Object-Oriented Serpent2-SUBCHANFLOW Coupling and Verification with Problem 6 of the VERA Core Physics Benchmark

Manuel Garcia, Diego Ferraro (KIT), Ville Valtavirta (VTT), Uwe Imke (KIT), Riku Tuominen (VTT), Victor Hugo Sanchez-Espinoza, Luigi Mercatali (KIT)

Detailed Modelling of the Expansion Reactivity Feedback in Fast Reactors Using OpenFOAM

Carlo Fiorina, Stefan Radman, Muhammed-Zahid Koc (EPFL), Andreas Pautz (EPFL, PSI)

3-D Coupled PARCS/ATHLET Transient Simulation of SFR Using Detailed Expansion Modeling

J. Bousquet, A. Seubert, R. Henry (GRS)

Shapley and Johnson Values for Sensitivity Analysis of PWR Power Distribution in fast Fluence Calculation

L. Clouvel, P. Mosca, J.-M. Martinez, G. Delipei (CEA)

Perturbation and Sensitivity of the Time Eigenvalue by a Generalized Iterated Fission Probability Method

A. Jinaphanh, A. Zoia (CEA)

Computing Adjoint-Weighted Tallies with TRIPOLI-4 Using the Wielandt Method

A. Jinaphanh, A. Zoia (CEA)

Uncertainty Quantification On Feedback and Safety Parameters of Lead-Cooled Fast Reactors

I. Trivedi, J. Hou (NCSU), G. Grasso (ENEA), K. Ivanov (NCSU)

Implementation of Random Sampling for ACE-Format Cross Sections Using FRENDY and application to Uncertainty Reduction

Ryoichi Kondo, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.), Kenichi Tada (JAEA)

Uncertainty in the DPA of a B&B Core Due to Uncertainty in the Neutron Spectrum

Chris Keckler, Massimiliano Fratoni, Ehud Greenspan (U. C., Berkeley)

Higher Order Accurate k-Eigenvalue Sensitivity Estimation Using the Complex-Step Derivative Method

Zeyun Wu (Virginia Commonwealth), James C. Newman III (Univ. Tenn., Chattanooga), Arthur C. Taylor III (Old Dominion)

Kinetics Parameter Estimation for Initially Subcritical Systems in the Monte Carlo Fixed Source Calculations

Hyung Jin Shim, Donghun Kim (Seoul Natl Univ–Korea)

Application of Various Superhomogenization (SPH) Methods for Method of Characteristics

Kento Sawada, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

Modal Analysis of 3D Full-Core Inhomogeneous Adjoint Nodal Equations and Associated Iterative Solution Processes

René van Geemert (Framatome)

Impact of Control Rod History on Physics Parameters in a Soluble-Boron-Free Small-Sized Pressurized Water Reactor

Maxime Guyot , Vincent Gautier-Ottou (CEA)

Performance Analysis of Zernike-Based FETs on a 2D PWR Pin Cell

Zhuoran Han, Benoit Forget, Kord Smith (MIT)

Transient Fission Matrix Analysis of Rod Drop Experiments in Coupled Cores for Addressing High Dominance Ratio Configurations

K. Routsonis, P. Blaise, J. Tommasi, G. Valocchi (CEA)

2D Core Calculation Based on the Method of Dynamic Homogenization

Antonio Galia, Igor Zmijarevic, Richard Sanchez (CEA)

On the Prompt Eigenvalue Reconstruction from Subcritical Experiments: An Application to KUCA Reactor

N. Chentre (INFN—Genova), P. Saracco (INFN—Genova, Centro Fermi), S. Dulla, Piero Ravetto (Politecnico di Torino)

Burnup Adaptation Model in STREAM/RASTK Code System

Peng Zhang, Jiwon Choe, Sooyoung Choi, Deokjung Lee (UNIST)

Application of the Coordinate Transformation in Nodal Diffusion Calculations of Radially Expanding SFR Cores

E. Nikitin, E. Fridman (Helmholtz-Zentrum Dresden-Rossendorf)

Application of the Superhomogenization Method in the STREAM/RASTK Code System for Pin-By-Pin Core Analysis

Peng Zhang, Jinsu Park, Jiwon Choe, Sooyoung Choi, Deokjung Lee (UNIST)

EPR Fuel Cycle Depletion with Pin-By-Pin Code Tortin and Nodal Code SIMULATE5

P. Mala, A. Pautz, H. Ferroukhi (PSI)

Coupled Deterministic and Monte Carlo Neutronics for Vessel Fluence Calculations

Shane C. Henderson, Tara M. Pandya, Shane Stimpson, Ben Collins (ORNL)

Verification and Validation of McCARD code for VHTR Application

Sung Hoon Choi, Chang Keun Jo, Tae Young Han (KAERI)

Application of Preconditioned Conjugate Gradient Method to Fine Mesh Rebalance for Accelerating DSA Equation on Tetrahedral Meshes

Habib Muhammad, Ser Gi Hong (Kyung Hee Univ.)

A Modified Least-Squares Finite Element Method for Solving the Boltzmann Transport Equation

Liangzhi Cao, Chao Fang, Hongchun Wu (Xi'an Jiaotong Univ.)

Acceleration of Source Iteration Using the Dynamic Mode Decomposition

Ryan G. McClarren (Notre Dame), Terry S. Haut (LLNL)

3D Whole-Core Adjoint Neutron Flux Calculation Using 2D/1D Method via Multi-Level CMFD Acceleration

Chen Hao, Kaijie Zhu, Le Kang, Ji Ma (Harbin Univ.), Yunlin Xu (Purdue)

Nonlinear Elimination Applied to Radiation Transport

Thomas A. Brunner, Paul F. Nowak (LLNL)

SDA: A Semilinear CMFD-Like Transport Acceleration Scheme Without D-hat

Zackary Dodson, Nickolas Adamowicz, Brendan Kochunas, Edward Larsen (Univ. Michigan)

The Response Matrix Acceleration Method for the Discrete-Ordinate Transport Equation

Wesley Ford, Emiliano Masiello, Christophe Calvin (CEA), François Fevotte, Bruno Lathuiliere (EdF)

SERPENT and TRIPOLI4® Transient Calculations Comparisons for SEVEral Reactivity Insertion Scenarios in a 3D PWR Minicore Benchmark

Diego Ferraro (KIT), Margaux Faucher, Davide Mancusi, Andrea Zoia (CEA), Ville Henrikki Valtavirta, Jaakko Leppänen (VTT), Victor Hugo Sanchez-Espinoza (KIT)

A Fully Analytic Coupled Thermal-Neutronics Benchmark and its Application to Monte Carlo Simulation

Kyle E. Remley, David P. Griesheimer (NNL)

BWR Spacer Grid Modeling Using SERPENT 2 / STAR-CCM+ Coupling

Alexander Bennett, George Bache, Nicolas Martin, Jaron Senecal (Framatome)

Development of Monte Carlo Multi-Physics Code MCS for Power Reactor Analysis at UNIST

Hyunsuk Lee, Wonkyeong Kim, Peng Zhang, Matthieu Lemaire,  Azamat Khassenov, Yunki Jo, Jinsu Park (UNIST), Jiankai Yu (Tsinghua Univ), Deokjung Lee  (UNIST)

Variance Overestimation in Monte Carlo Multi-Physics Simulation

Hyunsuk Lee, Peng Zhang, Deokjung Lee (UNIST)

Single-Batch Monte Carlo Multiphysics Coupling

Miriam A. Kreher, Benoit Forget, Kord Smith (MIT)

Multiphysics Steady-State Simulation the High Temperature Test Reactor with MAMMOTH, BISON and RELAP-7

Vincent Laboure, Javier Ortensi, Yaqi Wang, Sebastian Schunert, Frederick Gleicher, Mark DeHart, Richard Martineau (INL)

Reduced-Order Modeling of Parametrized Multi-Physics Computations for the Molten Salt Fast Reactor

P. German, J. C. Ragusa (Texas A&M), C. Fiorina (EPFL), M. Tano Retamales (Texas A&M)

A Discontinuous Galerkin FEM Multi-Physics Solver for the Molten Salt Fast Reactor

Marco Tiberga, Danny Lathouwers, Jan Leen Kloosterman (Delft Univ.)

Impact of Neutronic Parameters in a Loss-Of-Flow Transient Simulation of a Low-Void Reactivity Sodium-Cooled Nuclear Reactor

Bastien Faure, Pascal Archier, Pierre Sciora, Giorgio Valocchi, Laurent Buiron, Jean-Baptiste Droin, Vincent Pascal (CEA)

Analysis of Methodologies for the Coupling of Multi-Physics Phenomena in the Quasi-Static Approach to Nuclear Reactor Dynamics

D. Caron, A, Calloo, J,-C, Le Pallec, C, Patricot (CEA)

Development of Regulatory Compliant Coupled Neutronics-Thermohydraulics Models for Molten Salt Reactors

Claire Henriroux, Esben Bryndt Klinkby, Bent Lauritzen (Technical Univ. Denmark), Andreas Vigand Pedersen (Seaborg Technologies)

CAPP/GAMMA+ Coupled Code System for Transient Analysis of a Block-Type HTGR Core

Seungsu Yuk, Nam-il Tak, Jeong-Hun Lee, Hong Sik Lim, Jin Young Cho, Chang Keun Jo (KAERI)

Data Assimilation Using Subcritical Measurement of Prompt Neutron Decay Constant

Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

Calculation Method of Estimated Criticality Lower-Limit Multiplication Factor Using the Bootstrap Method

Takuto Hayashi, Tomohiro Endo, Akio Yamamoto (Nagoya Univ.)

Small Sample Reactivity Worths Calculation: Exact Perturbation Theory and Monte Carlo Transport

G. Truchet, P. Leconte (CEA)

Eigenvalue Sensitivity in Monte Carlo Simulations to Nuclear Data Parameters Using the Multipole Formalism

A. Alhajri, B. Forget (MIT)

Monte Carlo Estimates of Alpha-Eigenvalue Sensitivities via Differential Operator Sampling

Timothy P. Burke, Colin J. Josey (LANL), Brian C. Kiedrowski (Univ. Michigan)

Intrusive Uncertainty Quantification for Applications in Fluid Dynamics

Jonas Kusch, Jannick Wolters, Martin Frank (KIT)

Application of Markov Chain Monte Carlo for Uncertainty Quantification in Quantitative Imaging Problems

Keith C. Bledsoe, Matthew A. Jessee, Matthew A. Blackston (ORNL), Justin R. Knowles (Y-12), Klaus-Peter Ziock, Jordan P. Lefebvre (ORNL)

Development of Quasi-Static Capabilities for CORPUS-APOLLO3®

D. Caron, A. Calloo, J.-C. Le Pallec, C. Patricot (CEA)

Monte Carlo Calculations of the Burst Wait Time of Fast Burst Reactors Using MCATK

Travis J. Trahan (LANL)

Spatial Localization of Perturbation Propagation in LWRs Using Causality and Connectivity Analysis

D. Chionis (PSI, EPFL), A. Dokhane, H. Ferroukhi (PSI), A. Pautz (PSI, EPFL)

Leakage Feedback Method for Spectral Correction in Pin-Homogenized Multi-Group Core Calculations

Hyunsik Hong, Han Gyu Joo (Seoul Natl Univ.)

Frequency-Domain Stability Analysis of Reactivity Feedback Mechanisms

Doron Sivan, Erez Gilad (Ben-Gurion Univ.), Shai Kinast (NRCN)

Improvements of CMFD Acceleration Capability of OPENMOC

Wenbin Wu (MIT, Nuclear Power Inst. China), Guillaume Giudicelli, Kord Smith, Benoit Forget (MIT), Dong Yao, Qi Luo (Nuclear Power Inst China)

Estimation of Corner Flux in Rectangular Geometry

P. M. Bokov, D. Botes, D. I. Tomasevic (South African Nucl. En. Corp.)

The Residual Source Spatial Discretization Error Estimator for DGFEM-1 SN Neutron Transport Method

Nathan H. Hart, Yousry Y. Azmy (NCSU)

A Discrete Ordinates Solver with Diffusion Synthetic Acceleration for Simulations of 2-D and 2-Energy Group Neutron Noise Problems

Huaiqian Yi, Paolo Vinai, Christophe Demazière (Chalmers Univ.)

Analysis of Material Fluxes in Markov Mixtures

C. Larmier, S. Lemaire, E. Masiello, D. Riz, A. Zoia

An Extension of Conditional Point Sampling to Quantify Uncertainty Due to Material Mixing Randomness

Emily H. Vu (U. C., Berkeley), Aaron J. Olson (SNL)

An Extension of Conditional Point Sampling to Multi-Dimensional Transport

Aaron Olson (SNL), Emily Vu (U. C., Berkeley)

Verification of a Monte Carlo Levermore-Pomraning Algorithm for Spatially-Inhomogeneous Binary Stochastic Media

Patrick S. Brantley (LLNL), Patrick F. O'Rourke, Anil K. Prinja (Univ. New Mexico)

Uncollided-Flux Treatment for Discrete-Ordinate Radiation Transport Solutions in the Rattlesnake Code System

Logan Harbour, Jean Ragusa (Texas A&M), Yaqi Wang, Sebastian Schunert, Derek Gaston, Mark DeHart (INL)

A Sweep-Based Domain Decomposition and Task Schedule for Discrete Ordinates Transport

Troy L. Becker (NNL)

SN Transport on GPUs with PARTISN

Randal S. Baker, R. Joseph Zerr, Daniel J. Magee (LANL)

Mitigation of Communication Latency Based Slowdowns in the PIDOTS Massively Parallel SN Transport Code

Raffi Yessayan, Yousry Y. Azmy (NCSU), Joe Zerr (LANL), Sebastian Schunert (INL)

Porting Teton, a Discrete-Ordinates Thermal Radiative Transfer Code, to Sierra

P. Nowak, A. Black (LLNL), S. Rennich (NVIDIA), D. Appelhans (IBM), R. Chen, T. Haut (LLNL), P. Maginot (LANL), T. Bailey, P. Brown, A. Kunen, J. Loffeld, B. Tagani (LLNL)

Adding a Third Level of Parallelism to OpenMOC, an Open Source Deterministic Neutron Transport Solver

Guillaume Giudicelli (MIT), Wenbin Wu (Nuclear Power Inst. China), Colin Josey (LANL), Kord Smith, Benoit Forget (MIT)

Approaches to Load Balancing Massively Parallel Transport Sweeps on Unstructured Grids

Tarek Habib Ghaddar, Jean C. Ragusa, Marvin L. Adams (Texas A&M)

Status of LLNL Monte Carlo Transport Codes on Sierra GPUs

M. S. McKinley, R. Bleile, P. S. Brantley, S. Dawson, M. O’Brien, M. Pozulp, D. Richards (LLNL)

Development and Test of a Hybrid Probabilistic-Deterministic Framework Based on the Interface Current Method

H. Yi, C. Demaziere, P. Vinai (Chalmers Univ.), J. Leppänen (VTT)

Beam Calculation Method for a Neutron Camera

U. Steinitz, A. Krakovich, I. Neder (Soreq NRC)

Predicting Monte Carlo Tally Variance and Calculation Time when using Forced-flight Variance Reduction—Theory

Joel A. Kulesza (LANL, Univ. Michigan), Clell J. Solomon (LANL), Brian C. Kiedrowski (Univ. Michigan)

Predicting Monte Carlo Tally Variance and Calculation Time when using Forced-flight Variance Reduction—Verification

Joel A. Kulesza (LANL, Univ. Michigan), Clell J. Solomon (LANL), Brian C. Kiedrowski (Univ. Michigan)

Computing Alpha Eigenvalues Using the Fission Matrix

Colin Josey, Forrest B. Brown (LANL)

Verification of the Fission Matrix Decomposition Method Against Two Axially Heterogeneous Problems

S. Terlizzi, D. Kotlyar (Georgia Tech)

Ray Effects Mitigation Through Monte Carlo Coupling for Detector Problems

Nicholas F. Herring (Univ. Michigan), Raffi A. Yessayan (NCSU), Kyle A. Beyer, Robert J. Fonti, Evan S. Gonzalez, Evan C. Leppink, Blake D. Rucinski (Univ. Michigan), Sebastian Schunert (INL), Yousry Y. Azmy (NCSU), Brian C. Kiedrowski (Univ. Michigan)

X-CMFD: A Robust Iteration Scheme for CMFD-Based Acceleration of Neutron Transport Problems with Nonlinear Feedback

Qicang Shen, Nicholas Adamowicz, Brendan Kochunas, Edward Larsen (Univ. Michigan)

Relationship Between Relaxation and Partial Convergence of Nonlinear Diffusion Acceleration for Problems with Feedback

Qicang Shen, Nicholas Adamowicz, Brendan Kochunas (Univ. Michigan)

Challenging Test Problems for Coupled Transient Simulations of Pressurized Heavy Water Reactors

A. Trottiern, N. Aydemir (CNL), M. Krause (IAEA), M. Dahmani (SNC-Lavalin), D. Serghiuta (Canadian Nuclear Safety Commission)

Noble Metal Mass Transport Model for Molten Salt Reactor Analysis in VERA-CS

Samuel A. Walker (RPI), Zack Zachary Taylor (Univ. Tennessee), Robert Salko, Benjamin Collins (ORNL), Wei Ji (RPI)

A Projective Method for Solving the Single-Group Space-Time Neutron Kinetics Equations with Precursor Advection

Aaron J. Reynolds, Todd S. Palmer (Oregon State)

A Three Temperature, Multi-Dimensional, Multi-Frequency, Nonlinearly Coupled Thermal Radiation Transport Solver

Hans Hammer, HyeongKae Park, Luis Chacon (LANL)

Verification & Validation of MCS Multi-Physics Analysis Capability for OPR-1000 Multi-Cycle Operation

Vutheam Dos, Hyunsuk Lee, Jiwon Choe, Matthieu Lemaire (UNIST), Ho Cheol Shin, Hwan Soo Lee (KHNP), Deokjung Lee (UNIST)

Safety Parameters Uncertainty and Sensitivity Analysis for High Flux Reactor at Institut Laue Langevin

D. Portinari (LPSC, Politecnico di Milano), M. Aufiero (Milano Multiphysics), Y. Calzavara (Laue Langevin), A. Cammi, S. Lorenzi (Politecnico di Milano), A. Bidaud (LPSC)

Development and Verification of Perturbative Methods in the APOLLO3® Code: Sensitivity Analysis and Uncertainty Quantification Applied to Pressurized-Water and Sodium Fast Reactors

Pascal Archier, Ansar Calloo, Giorgio Valocchi, Bastien Faure, Jean-Marc Palau (CEA)

Geometric Uncertainty Quantification and Robust Design for 2D Satellite Shielding

Shawn D. Pautz, Brian M. Adams, Don E. Bruss (SNL)

Second Derivative of an (?,n) Neutron Source with Respect to Constituent Isotope Densities

Jeffrey A. Favorite (LANL)

Nuclear Data Uncertainty Quantification in Molten Salt Reactors with xGPT

Nicolò Abrate (Politecnico di Torino), Manuele Aufiero (Politecnico di Milano), Sandra Dulla (Politecnico di Torino), Luca Fiorito (SCK/CEN)

Embedded Monte Carlo Neutron Random Walk and Uncertainty in Nuclear Cross Sections

Pablo Ducru, Jingang Liang (MIT), Vladimir Sobes (ORNL), Abdulla Alhajri, Isaac Meyer, Benoit Forget, Kord Smith (MIT)

SCALE/Sampler Sensitivity Indices

F. Bostelmann, D. Wiarda, W. A. Wieselquist, B. T. Rearden (ORNL)

Convergence Limits in Perturbation Theory

Nicolò Abrate, Sandra Dulla, Piero Ravetto (Politecnico di Torino), Giovanni Bruna (NINE Engineering)

Multigrid Algorithms with Projection and Prolongation over Elements of the Phase Space for K-Eigenvalue Transport Problems

Luke R. Cornejo, Dmitriy Y. Anistratov (NCSU)

Revisiting Mini-Max Polynomial Approximation Method for Nuclear Fuel Depletion Calculation

Go Chiba (Hokkaido Univ.), Yasunori Ohoka, Kento Yamamoto, Hiroaki Nagano (Nuclear Fuel Industries)

A Linear Diffusion-Acceleration Method for k-Eigenvalue Transport

Anthony P. Barbu, Marvin L. Adams (Texas A&M)

Derivation of Multigroup Diffusion Coefficients to Preserve Moments of Neutron Migration

Eshed Magali, Edward Larsen (Univ. Michigan)

Continuous Energy Comet Solution to Advanced Burner Test Reactor Benchmark Problem

Dingkang Zhang, Farzad Rahnema (Georgia Tech)

Generalized Equivalence Theory used with Linear Sources in the Method of Characteristics for Neutron Transport

Guillaume Giudicelli, Kord Smith, Benoit Forget (MIT)

POD-Galerkin Reduced Order Model of the Boussinesq Approximation for Buoyancy-Driven Enclosed Flows

K. Star (SCK•CEN, Ghent Univ.), G. Stabile (SISSA), S. Georgaka (Imperial College London), F. Belloni (SCK•CEN), G. Rozza (SISSA) J. Degroote (Ghent Univ.)

Application of Reduced Order Model for Uncertainty Quantification of PWR LOCA Analysis

Ikuo Kinoshita (Institute of Nuclear Safety System)

Dynamic Mode Decomposition for Subcritical Metal Systems

Zachary K. Hardy, Jim E. Morel (Texas A&M), Cory Ahrens (LANL)

Model Order Reduction for SN Radiation Transport

Patrick A. Behne, Jean C. Ragusa, Jim E. Morel (Texas A&M)

Reduced Order Modeling of the TWIGL Problem Using Proper Generalized Decomposition

Anthony L. Alberti, Todd S. Palmer (Oregon State)

Investigative Study on Impact of Modeling Uncertainties in Uncertainty Quantification of Neutronics Core Simulation

Dongli Huang, Hany S. Abdel-Khalik (Purdue)

Proper Generalized Decomposition of Multigroup Neutron Diffusion with Separated Space-Energy Representation

Zachary M. Prince, Jean C. Ragusa (Texas A&M)

Memory Footprint Reduction of a Multi-Group DPN Transport Operator for 3D MOC Acceleration

D. Sciannandrone (CEA), L. Graziano (FRAMATOME), S. Santandrea (CEA)

Performance of Parallel Approximate Ideal Restriction Multigrid for Transport Applications

Joshua Hanophy, Jim E. Morel (Texas A&M), Ben Southworth, Tom Manteuffel (Univ. Colorado), Ruipeng Li (LLNL)

Impact of Load Balancing on Parallel Performance with Haar Wavelets Angular Adaptivity

Ioannis Nikiteas, Steven Dargaville, Christopher C. Pain (Imperial College London), Paul N. Smith (ANSWERS), Richard P. Smedley-Stevenson (Imperial College London, AWE)

An Event-Based Algorithm for Random Ray Neutral Particle Transport on GPUs

John R. Tramm, Andrew R. Siegel, Paul K. Romano (ANL)

Developing a Mini-App for Exploring Algorithms for Unstructured Mesh Deterministic Discrete Ordinates Transport on Many-Core Architectures

Tom Deakin, Simon McIntosh-Smith (University of Bristol), Justin Lovegrove, Richard P. Smedley-Stevenson, Andrew Hagues (AWE)

VEXS, An Open Platform for the Study of Continuous-Energy Cross-Section Lookup Algorithms on GPU's

Forrest Shriver (Univ. Florida), Seyong Lee, Steven Hamilton (ORNL), Justin Watson (Univ. Florida), Jeffrey Vetter (ORNL)

Porting 3D Discrete Ordinates Sweep Algorithm in Ardra to CUDA

A. Kunen, J. Loffeld, A. Black, R. Chen, P. Nowak, T. Haut, T. Bailey, P. Brown (LLNL), S. Rennich (NVIDIA), P. Maginot (LANL), B. Tagani (LLNL)

Validation of APOLLO2-A Against SERPENT2 on BWR Lattices

Alexander Bennett, Nicolas Martin, Martin Schneider (Framatome)

Multi-Cycle Depletion with the GRS Core Simulator KMACS: BEAVRS Cycles 1 and 2

Matias Zilly, Jeremy Bousquet (GRS GmbH)

SPERT III E-Core Critical Experiment Benchmarks Calculation with NECP-X and KENO-VI

Chen Zhao (Xi'an Jiaotong Univ., Univ. Michigan), Qicang Shen (Univ. Michigan), Zhouyu Liu, Lu Cao (Xi'an Jiaotong Univ.), Thomas Downar (Univ. Michigan), Liangzhi Cao (Xi'an Jiaotong Univ.)

Detailed Neutronic Modelling of the CROCUS Research Reactor Using APOLLO3® Transport Code

Igor Zmijarevic (CEA), Mereke Tontayeva (IMT Atlantique), Daniele Tomatis, Zarko Stankovski (CEA)

Towards the Validation of Neutron Noise Simulators: Qualification of Data Acquisition Systems

A. Rais (EPFL), V. Lamirand (EPFL, Chalmers Univ.), O. Pakari, A. Laureau (EPFL), J. Pohlus, C. Pohl (TÜV Rheinland), S. Hübner (Technische Univ. Dresden), M. Hursin (EPFL, PSI), C. Demazière (Chalmers Univ.), A. Pautz (EPFL, Chalmers Univ.)

Implementation of Dynamic Control Rod Reactivity Measurement Method to STREAM/RAST-K 2.0

Eun Jeong (UNIST), Eunki Lee, Ho Cheol Shin (KHNP), Deokjung Lee (UNIST)

SERPENT Validation Using GIACINT Facility Experimental Data from a Control Rod Insertion Transient

A. Talamo, Y. Gohar (ANL), V. Valtavirta, J. Leppänen (VTT), S. Sikorin, S. Mandzik, S. Polazau, T. Hryharovich (Joint Institute for Power and Nuclear Research - Sosny)

3-D Modelling of a Superphénix Benchmark with SERPENT and PARCS for coupled simulation with PARCS/ATHLET

R. Henry, A. Seubert (GRS)

BEAVRS Benchmark Analysis by DeCART Standalone and DeCART/MATRA Multi-physics Code Coupling Calculations

Ho Jin Park, Seong Jin Kim, Hyuk Kwon, Jin Young Cho (KAERI)

An Advanced Experimental Validation Methodology of Multiphysics Calculation Tools on CABRI Transients

J.-M. Labit, N. Marie, J.-P. Hudelot (CEA), E. Merle (CNRS)

Measurement of the Gas Velocity in a Water-Air Mixture in CROCUS by Neutron Noise Technique

Mathieu Hursin (PSI, EPFL), Oskari Pakari (EPFL), Gregory Perret (PSI), Pavel Frajtag, Vincent Lamirand (PSI, EPFL), Imre Pázsit, Victor Dykin (Chalmers Univ.), Gabor Por (Budapest Univ.), Henrik Nylen (Chalmers Univ., Ringhals AB), Andreas Pautz (PSI, EFPL)

Bayesian Calibration of Cross-Sections Using Plant Operating Data

Bassam A. Khuwaileh, Paul J. Turinsky (NCSU)

Uncertainty Analysis Methodology for Multi-Physics Coupled Rod Ejection Accident

G.-K. Delipei (CEA), J. Garnier (Ecole Polytechnique), J.-C. Le Pallec, B. Normand (CEA)

Comparative Analysis of Solutions of Neutronics Exercises of the LWR UAM Benchmark

J. Hou, C. Maras, C. Gozum, M. Avramova, K. Ivanov (NCSU)

Characterization of Spent PWR Fuel for Decay Heat, Neutron and Gamma-Ray Emission: Code Comparison

Gašper Žerovnik (EC-JRC Geel), Klemen Ambroži?, Dušan ?ali? (Jožef Stefan Institute), Luca Fiorito, Kevin Govers, Augusto Hernandez Solis (Belgian Nuclear Research Centre (SCK•CEN)), Bor Kos, Marjan Kromar (Jožef Stefan Institute), Peter Schillebeeckx (EC-JRC Geel), Alexey Stankovskiy (Belgian Nuclear Research Centre (SCK•CEN))

Uncertainty Quantification of LWR-PROTEUS Phase II Experiments Using CASMO-5

Mathieu Hursin (PSI), Jinsu Park, Wonkyeong Kim (UNIST), Daniel Siefman (EPFL), Gregory Perret, Alexander Vasiliev, Dimitri Rochman, Andreas Pautz, Hakim Ferroukhi  (PSI), Deokjung Lee (UNIST)

Impact of Spatial Coupling Schemes and Perturbation Options on Uncertainty Quantification of PWR Core Simulation

Kaiyue Zeng, Jason Hou, Kostadin Ivanov (NCSU)

Impact of Implicit Effects on Uncertainties in SPERT-III Rod Ejection Accident Experiments

A. Dokhane, M. Hursin, A. Vasiliev, H. Ferroukhi (PSI), G. Grandi (Studsvik Scandpower)

Uncertainty Quantification of Model-Form and Predictive Uncertainties in Nuclear Codes Using Bayesian Framework

Majdi I. Radaideh, Katarzyna Borowiec, Tomasz Kozlowski (Univ. Illinois)

Native MOOSE Meshing Capability for Light Water Reactor Analysis

Jieun Lee (Texas A&M), Sebastian Schunert, Derek Gaston, Yaqi Wang, Javier Ortensi, Mark DeHart (INL), Yassin A. Hassan (Texas A&M)

A Metaheuristic Optimization Tool for High Flux Isotope Reactor Low-Enriched Uranium Design

I. Variansyah (Univ. Michigan), B. R. Betzler, D. Chandler, G. Ilas (ORNL), W. R. Martin (Univ. Michigan

Implementation of Depletion Architecture in the MAMMOTH Reactor Physics Application

Olin Calvin (Univ. Florida), Javier Ortensi, Sebastian Schunert, Yaqi Wang, Mark DeHart (INL), Sedat Goluoglu (Univ. Florida)

Performance Improvements to the 2D/1D Subplane Method in MPACT

Shane Stimpson, Aaron Marc Graham, Benjamin Collins (ORNL)

Application of the Method of Manufactured Solutions to the C5G7 Problem to Verify a Two-Dimensional Multi-Group Neutron Transport Solver

Jipu Wang, William Martin (Univ. Michigan), Benjamin Collins (ORNL)

Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-Group Libraries for Advanced Reactor Analysis

Kang Seog Kim, Friederike Bostelmann, Andrew M. Holcomb, Germina Ilas, William A. Wieselquist (ORNL)

Böhnel Multiplicity Formulae Beyond the Point Model

Imre Pázsit (Chalmers Univ.), Lénárd Pál (Hungarian Academy of Sciences), Andreas Enqvist (Univ. Florida)

Multiplicity Counting Using the Two- and Three Point Statistics of Fission Chamber Signals—Theory and Experimental Demonstration

L. Nagy, I. Pázsit (Chalmers Univ.), L. Pál (Hungarian Academy of Sciences), G. Klujber, M. Szieberth (Budapest Univ. Technol. Econ.)

Neutron-Induced Damage Simulations: Novel Nuclear Data Forms and Metrics for Material Sciences

Jean-Christophe Sublet (IAEA), Mark Gilbert (UKAEA)

Efficient Surrogate for Low Energy Damage Effects in Polyatomic Materials

Sebastian Schunert, Daniel Schwen, Daniel J. Vanwasshenova (INL)