International Conference on Physics of Reactors 2022 (PHYSOR 2022)

Full Issue

Fourier Analysis of Continuous Fractional Diffusion Synthetic Acceleration Schemes in Slab Geometry

Massimiliano Rosa (Penn State)

A Flexible Linear Diffusion Acceleration to k-Eigenvalue Neutron Transport with SN Discontinuous Finite Element Method

Yaqi Wang (INL), Zachary Prince (INL), Logan Harbour (INL), Sebastian Schunert (INL)

Analysis of Cell-Based Diffusion Acceleration for the Slice Balance Approach

Michael W. Hackemack (Naval Nuclear Laboratory)

Anderson Acceleration Stability in NDA-Accelerated k-Eigenvalue Problems

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

Transient Analysis of a Micro-Reactor Using the DireWolf Code Suite

Nathan Roskoff (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Alex Levinsky (Westinghouse Electric Co.), Vincent Laboure (INL), Jackson Harter (INL), Adam Zabriskie (INL), Lise Charlot (INL)

XE-100 Modeling and Simulation for Neutronic Analysis in MCNP6.2

Austin Carter (INL), Travis Lange (INL), Paolo Balestra (INL), Gerhard Strydom (INL), Sonat Sen (X-Energy), Raymond Wang (X-Energy)

Multiphysics Analysis System for Heat Pipe Cooled Micro Reactors Employing PRAGMA-OpenFOAM-ANLHTP

Jaeuk Im (Seoul Nat'l Univ.), Myung Jin Jeong (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Kyung Min Kim (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)

Stability Margin Analysis of the Holos-Quad Microreactor Design

Shai Kinast (Nuclear Research Center Negev), Claudio Filippone (HolosGen), Brendan Kochunas (Univ. Michigan)

Investigation of the Impact of Difference Between FRENDY and NJOY2016 on Neutronics Calculations

Michitaka Ono (Global Nuclear Fuel-Japan), Masayuki Tojo (Global Nuclear Fuel-Japan), Kenichi Tada (Japan Atomic Energy Agency), Akio Yamamoto (Nagoya Univ.)

The LLNL Nuclear Data Infrastructure for the GNDS Data Format

G. Gert (LLNL), M.A. Descalle (LLNL), C.M. Mattoon (LLNL), B.R. Beck (LLNL)

Development of Nuclear Data Processing Code FRENDY Version 2

Kenichi Tada (Japan Atomic Energy Agency), Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Go Chiba (Hokkaido Univ.), Michitaka Ono (Global Nuclear Fuel-Japan), Masayuki Tojo (Global Nuclear Fuel-Japan)

Impacts of Processing Decisions on TNSL Cross Sections and Their Applications

Ali Dreyfuss (LLNL), Bret Beck (LLNL), Caleb Mattoon (LLNL), Peter Brown (LLNL), Scott McKinley (LLNL), Marie-Anne Descalle (LLNL)

Comparative Critical Mass Calculations for NNL and ENDF/B-VIII.0 Zirconium Hydride Thermal Neutron Scattering Laws

J.L. Wormald (Naval Nuclear Laboratory), J.C. Holmes (Naval Nuclear Laboratory), M.L. Zerkle (Naval Nuclear Laboratory)

Constellation's Best Estimate Alternate Source Term Methodology Overview

B. Sarikaya (Constellation), J. Massari (Constellation), L. Wells (Constellation), S. Gardner (Constellation)

Study of Effect of PWR Cold Leg Temperature Gradient on Reactor Core Condition

Emre Tatli (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co. )

Comparisons of Nodal Diffusion and Whole-Core Transport Methods for Multiple Cycles of a Small Light Water Reactor

Jordan D. Rader (ORNL), Andrew T. Godfrey (ORNL), Aaron M. Graham (ORNL), Clayton D. Lietwiler (Holtec International), Hunter Smith (Holtec International), Malinda Saia (Holtec International)

Determination of the Spent Fuel Decay Heat with the VERA Core Simulator

Marjan Kromar (Jožef Stefan Institute), Andrew T. Godfrey (ORNL)

VERA Neutronics High-Fidelity Benchmark for a Modern PWR Core Design

Andrew T. Godfrey (ORNL), Benjamin S. Collins (Veracity Nuclear)

Multigroup Cross Section Generation Capability in Griffin

Hansol Park (ANL), Changho Lee (ANL), Yeon Sang Jung (ANL), Yaqi Wang (INL), Olin Calvin (INL), Javier Ortensi (INL)

Implementation of Hybrid Finite Element Method Based Transport Solver in Griffin

Yeon Sang Jung (ANL), Yaqi Wang (INL), Changho Lee (ANL), Hansol Park (ANL), Javier Ortensi (INL)

MOOSE Framework Enhancements for Meshing Reactor Geometries

Emily Shemon (ANL), Kun Mo (ANL), Yinbin Miao (ANL), Yeon Sang Jung (ANL), Scott Richards (ANL), Aaron Oaks (ANL), Shikhar Kumar (ANL)

Physics Demonstration and Verification of MOOSE Framework Reactor Module Meshing Capabilities

S. Kumar (ANL), K. Mo (ANL), E. Shemon (ANL), Y. Miao (ANL), N. Wozniak (ANL), Y. S. Jung (ANL)

High-Order Diamond Differencing Schemes for the Boltzmann Fokker-Planck Equation in 3D Cartesian Geometries

Charles Bienvenue (Polytechnique Montréal), Alain Hebert (Polytechnique Montréal)

New Modelling Capabilities in IDT

Francesco Filiciotto (CEA), Emiliano Masiello (CEA), Sandrine Lapuerta-Cochet (CEA), Roland Lenain (CEA)

On the Effect of Scalar Flux Weighting of Linearly Anisotropic Scattering Matrices in Few-Group Transport Calculations

B. Babcsány (Budapest Univ. Technology and Economics), Z. I. Böröczki (Budapest Univ. Technology and Economics), J. E. Maróti (Budapest Univ. Technology and Economics), M. Szieberth (Budapest Univ. Technology and Economics)

First-Collision Source Treatment for Ray Effect Mitigation in Discrete-Ordinate Radiation Transport Solutions

A. Christensen (LLNL), A. Kunen (LLNL), J. Loffeld (LLNL), P. Brown (LLNL), R. Vega (LLNL), M. Fratoni (Univ. California, Berkeley), M. Ishii (LLNL)

3D Spherical Functional Expansion Tallies in Serpent 2 Monte Carlo Code

Ana Jambrina (VTT Technical Research Centre of Finland), Jaakko Leppänen (VTT Technical Research Centre of Finland)

Implementation and Testing of the GPT Sensitivities in TRIPOLI-4®

A. Jinaphanh (CEA), C. Carabajal (CEA), A. Zoia (CEA)

Optimization of Particle Tracking Methods for Stochastic Media

Hunter Belanger (CEA), Coline Larmier (CEA), Davide Mancusi (CEA), Andrea Zoia (CEA)

Particle Transport in Markov Stochastic Mixtures with Spatial Gradients

Mikolaj Adam Kowalski (CEA), Coline Larmier (CEA), Johan Durand (CEA), Sebastien Lemaire (CEA), Andrea Zoia (CEA)

Status of the OECD/NEA Watts Bar Unit 1 Benchmark and Calculations of Local Reactor Core Power Data of the Zero Power Physics Tests

T. Albagami (NCSU), P. Rouxelin (NCSU), S. Palmtag (NCSU), M. Avramova (NCSU), K. Ivanov (NCSU)

Whole Core Analysis of OECD/NEA TVA-WB1 Benchmark Exercise 1 Using Continuous-Energy Monte Carlo Code MVP with JENDL-4.0u and ENDF/B-VII.0

Motomu Suzuki (Central Research Institute of Electric Power Industry)

OECD/NEA MPCMIV Benchmark -- Preliminary Fuel Performance Results

Quentin Faure (NCSU), Gregory Delipei (NCSU), Maria Avramova (NCSU), Kostadin Ivanov (NCSU)

Investigation of the OECD/NEA PWR MOX/Uo2 Core Transient Benchmark Using a Coupled Whole Core Pin-by-Pin Route in WIMS

Alan Charles (Jacobs), Magda Stefanowska (Jacobs), Jean Lavarenne (Jacobs), Brendan Tollit (Jacobs), Peter Smith (Jacobs)

A Preconceptual Design of an Inverted Stable-Salt Reactor

Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.)

Neutronic Design and Fuel Cycle Analysis of a Fluoride Salt-Cooled High Temperature Reactor (FHR)

Zuolong Zhu (Ohio State), Dean Wang (Ohio State)

Fast Modular Reactor Nuclear Design Parameters of Fuel Cycle and Power Distributions

Darrin Leer (General Atomics), Hangbok Choi (General Atomics), John Bolin (General Atomics), Alexander Dheming (General Atomics), Oscar Gutierrez (General Atomics), Ron Faibish (General Atomics)

Initital Development of a Generic Fluoride Salt-Cooled Reactor Model

Robert F. Kile (Univ. Tennessee, Knoxville), Friederike Bostelmann (ORNL), Steven E. Skutnik (ORNL), William A. Wieselquist (ORNL), Nicholas R. Brown (Univ. Tennessee, Knoxville)

Development and Benchmarking of Transient Nodal Code SIMULATE5-K Neutron Kinetics Solver

Tamer Bahadir (Studsvik Scandpower)

ANTARES: A New IRSN Computational Chain for Safety Analysis

F. Dubois (IRSN), M. Forestier (IRSN), G. Girault (IRSN), J.C. Jaboulay (IRSN), F. Jacq (IRSN), A. Sargeni (IRSN)

Thermal Feedback Coupling in a Transient Monte Carlo High-Order/Low-Order Scheme

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

Transient MOC with Frequency Transform and DSA on Unstructured Mesh

Gavin Ridley (MIT), Logan Harbour (INL), Benoit Forget (MIT), Derek Gaston (INL)

Evaluation of the GaAs Displacement Damage Metric Using Updated Nuclear Data

Nicholas Asper (Univ. Texas, Austin), Bill Charlton (Univ. Texas, Austin), Patrick J. Griffin (Sandia)

Thermal Scattering Law for Structure-Dependent-Doppler Broadening in FLASSH

J.P.W. Crozier (NCSU), N.C. Fleming (NCSU), A.I. Hawari (NCSU)

FLASSH 1.0: Thermal Scattering Law Evaluation and Cross Section Generation for Reactor Physics Applications

N.C. Fleming (NCSU), C.A. Manring (NCSU), B.K. Laramee (NCSU), J.P.W. Crozier (NCSU), E. Lee (NCSU), A.I. Hawari (NCSU)

Development of a Phonon-Based Sampling Method for Thermal Neutron Scattering Data

Amelia Trainer (MIT), Benoit Forget (MIT)

Linear Source Method of Characteristics in HELIOS2

Charles A. Wemple (Studsvik Scandpower), Rodolfo M. Ferrer (Studsvik Scandpower)

Performance Enhancement of Planar MOC Calculation in Hexagonal Geometries by Assembly-Wise Domain Decomposition

Seongchan Kim (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)

Neutron Diffusion Calculation in Heterogeneous Geometry Based on Local/Global Iteration Using Proper Orthogonal Decomposition

Masato Ito (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Yoshitada Masaoka (Nuclear Fuel Industries), Yasuhiro Kodama (Nuclear Fuel Industries), Hiroaki Nagano (Nuclear Fuel Industries)

Reduced-Order Modeling of Neutron Transport Separated in Energy by Minimax Proper Generalized Decomposition

Kurt Dominesey (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)

Predicting Deviations in Ex-Core Detector Response in Krško NPP During an Earthquake with Monte Carlo Neutron Transport Methods

T. Goričanec (Jožef Stefan Institute), A. Kavčič (Krško Nuclear Power Plant), M. Kromar (Jožef Stefan Institute), B. Krajnc (Krško Nuclear Power Plant), L. Snoj (Jožef Stefan Institute)

SERPENT 2 and TRIPOLI-4 Neutronics Benchmarking of the Jules Horowitz Reactor

Jussi Peltonen (VTT Technical Research Centre of Finland), David Blanchet (CEA)

Variance Reduction Techniques for Monte Carlo Neutron Noise Simulations

Hunter Belanger (CEA), Davide Mancusi (CEA), Andrea Zoia (CEA)

General Overview of Multiphysics Modeling and Simulation at CEA/DES/IRESNE Supporting Safety, Operating and Development of Nuclear Reactors and Facilities

Claire Vaglio-Gaudard (CEA), Isabelle Ramiere (CEA), Nathalie Seiler (CEA)

Development of a Calculation Framework Coupling Monte Carlo Neutronics, Subchannel Thermal-Hydraulics and 1.5D Fuel Thermo-Mechanics

Heikki Suikkanen (LUT Univ.), Ville Rintala (LUT Univ.)

Low Level Coupling Scheme Between Neutronics and Thermal-Hydraulics Based on Anderson Acceleration

Robin Delvaux (CEA), Cyril Patricot (CEA), Ansar Calloo (CEA)

Coupling of nTRACER to COBRA-TF for Full Core High-Fidelity Analysis of VVERs

Marianna Papadionysiou (Paul Scherrer Institute), Kim Seongchan (Seoul Nat'l Univ.), Mathieu Hursin (Paul Scherrer Institute), Alexander Vasiliev (Paul Scherrer Institute), Hakim Ferroukhi (Paul Scherrer Institute), Andreas Pautz (Paul Scherrer Institute), Han Gyu Joo (Seoul Nat'l Univ.)

Conceptual Design of Inverted Core Lead Bismuth Eutectic Fast Reactor for Marine Applications

Muhammad Farid Khandaq (Ulsan Nat'l Institute of Science and Technology), Tung Dong Cao Nguyen (Ulsan Nat'l Institute of Science and Technology), Eun Jeong (Ulsan Nat'l Institute of Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Feasibility of Lead-Bismuth-Cooled Fast Reactor with Fuel Shuffling Strategy

Tung Dong Cao Nguyen (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

LMFR Design and Optimization Methodology

Khaldoon A. Al-Dawood (NCSU), Scott P. Palmtag (NCSU)

Coupled Neutronic-Thermal-Hydraulic Simulations of the European SFR Core

B. Lindley (Univ. Wisconsin, Madison), F. Álvarez Velarde (CIEMAT), J. Bodi (Paul Scherrer Institute), A. Charles (Jacobs), E. Fridman (HZDR), J. Krepel (Paul Scherrer Institute), J. Lavarenne (Jacobs), K. Mikityuk (Paul Scherrer Institute), E. Nikitin (HZDR), A. Ponomarev (Paul Scherrer Institute), B. Tollit (Jacobs)

Simulation of Peach Bottom Turbine Trip Transients TT1, TT2 and TT3 with SIMULATE-3K

Chris Henry (Constellation), Gerardo M. Grandi (Studsvik), Boyan D. Ivanov (Constellation)

Simulation of Peach Bottom Turbine Trip Transient with RETRAN-3D Using BXFGEN

Phillip Gorman (Zachry Nuclear Engineering), Taylor Blyth (Zachry Nuclear Engineering), Darian King (Zachry Nuclear Engineering), Michael Howard (Zachry Nuclear Engineering), Chris Henry (Constellation), Boyan D. Ivanov (Constellation)

Development of the TREAT M2 Experiment as a Transient Benchmark

Akram S. Batikh (NCSU), Ayman I. Hawari (NCSU)

Bayesian Estimation of Cross-Section and Errors of Experiment and Calculation for Accurate Prediction of Neutronic Characteristics

Satoshi Takeda (Osaka Univ.), Takanori Kitada (Osaka Univ.)

On the Characterization of Biases Arising from Methods and Approximations Used for Sensitivity Analyses

A. Jiménez-Carrascosa (Univ. Politécnica de Madrid), N. García-Herranz (Univ. Politécnica de Madrid), O. Cabellos (Univ. Politécnica de Madrid)

Optimizing Group Structures Using Hierarchical Division

Andrew Till (LANL), Nathan Gibson (LANL), Thomas Saller (LANL)

Analytical Benchmark Solution for 1-D Neutron Transport Coupled with Thermal Conduction and Material Expansion

David P. Griesheimer (Naval Nuclear Laboratory), Gabriel Kooreman (Naval Nuclear Laboratory)

Investigations About Iso-Geometric Analysis for Self-Shielding Calculations with the Subgroup Method

Matthias H. Nezondet (Univ. Fukui), Willem F.G van Rooijen (Univ. Fukui)

Parallel Transport Sweeps on Two-Dimensional Cartesian and Hexagonal Grids

Atyab A. Calloo (Polytechnique Montreal), Alain Hebert (Polytechnique Montreal)

Energy Depostion in STREAM with Photon Transport

Nhan Nguyen Trong Mai (Ulsan Nat'l Institute of Science and Technology), Kyeongwon Kim (Ulsan Nat'l Institute of Science and Technology), Woonghee Lee (Ulsan Nat'l Institute of Science and Technology), Tuan Quoc Tran (Ulsan Nat'l Institute of Science and Technology), Siarhei Dzianisau (Ulsan Nat'l Institute of Science and Technology), Fathurrahman Setiawan (Ulsan Nat'l Institute of Science and Technology), Yunki Jo (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Application of Linear Prolongation to Coarse Mesh Finite Difference Acceleration in CASMO5

Rodolfo Ferrer (Studsvik Scandpower), Joshua Hykes (Studsvik Scandpower)

Generation of Group Constants at GRS for the Rostov-2 Benchmark

Romain Henry (GRS), Yann Périn (GRS), Anton Travleev (GRS)

Native Natural Circulation in VERA

Nicholas F. Herring (Univ. Michigan), Benjamin S. Collins (Univ. Texas, Austin), Thomas J. Downar (Univ. Michigan)

Quantification of the Importance of the Modeling Fidelity in the Best Estimate Plus Uncertainty Analysis

Gregory K. Delipei (NCSU), Agustin Abarca (NCSU), Pascal Rouxelin (NCSU), Maria Avramova (NCSU), Kostadin Ivanov (NCSU)

Extension of the High-Resolution Thermal-Hydraulics Code ESCOT to Hexagonal Core Geometries for Multi-Physics Calculations

Jorge Gonzalez-Amoros (Seoul Nat'l Univ.), Seongchan Kim (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)

Control Rod Modeling in Liquid Metal-Cooled Fast Reactors

Timothy M. Kiefer (NCSU), William C. Dawn (NCSU), Khaldoon Al-Dawood (NCSU), Scott Palmtag (NCSU)

Application of Monte Carlo Code Shift for MSBR Dose Rate Calculations

Yan Cao (ANL), Eva E. Davidson (ORNL), Benjamin R. Betzler (ORNL), Bo Feng (ANL)

Activation of Lead Coolant in Westinghouse Lead Fast Reactor

Alex Levinsky (Westinghouse Electric Co.), F. Franceschini (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), C. Stansbury (Westinghouse Electric Co.), M. Ickes (Westinghouse Electric Co.), Jun Liao (Westinghouse Electric Co.)

Stability Analysis of a One-Dimensional Multiphysics Model of a Molten Salt Fast Reactor

Maximilian Kraus (Technische Univ. Dresden), Marco Viebach (Technische Univ. Dresden), Carsten Lange (Technische Univ. Dresden), Antonio Hurtado (Institute of Power Engineering)

Using Griffin's Transmutation Solver to Calculate Radiation Damage

Micah Gale (INL), Olin Calvin (INL), Sebastian Schunert (INL)

High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method

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

Variable Dynamic Mode Decomposition for Estimating Time Eigenvalues in Nuclear Systems

Ethan Smith (Univ. Notre Dame), Ilham Variansyah (Univ. Notre Dame), Ryan G. McClarren (Univ. Notre Dame)

Initial Exploration of a Novel Transient Arrest System Involving Fuel Heating

Dean Price (INL), Micah Gale (INL), Mark Dehart (INL), Andrew Maile (INL), Joshua Peterson-Droogh (INL)

Nuclide Inventory Validation: Radiochemical Assay Data Quality and Modeling Challenges in Benchmark Models Development

Germina Ilas (ORNL), Bruce Bevard (ORNL), Jeffrey Delashmitt (ORNL), Joseph Giaquinto (ORNL), Cole Hexel (ORNL), Shalina Metzger (ORNL), Benjamin Roach (ORNL), Kayron Rogers (ORNL), Alex Zirakparvar (ORNL)

Impact of Fission Yield Covariance Matrices on Decay Heat Uncertainty Quantification with the DARWIN2 Package

M. Tiphine (CEA), V. Vallet (CEA)

Testing Nuclear Data Libraries with Burnup for Reactor Applications

R. Ichou (IRSN), N. Leclaire (IRSN), L. Leal (IRSN)

Nuclear Data Uncertainty Quantification for the Nuclide Inventory of a Calvert Cliffs Spent Fuel Sample

F. Grimaldi (SCK-CEN), L. Fiorito (SCK-CEN), P. Romojaro (SCK-CEN), A. Hernandez-Solis (SCK-CEN)

Assessment of Nuclear Data Needs for Advanced Reactor Demonstrations: Application to the Molten Chloride Reactor Experiment (MCRE)

G. Palmiotti (INL), T. Cisneros (TerraPower), J. C. Gehin (INL)

Contributions to the IRPhEP Handbook Since PHYSOR 2018

John D. Bess (JFoster & Assoc.), Tatiana Ivanova (OECD NEA), Ian Hill (OECD NEA), Julie-Fiona Martin (OECD NEA), Lori Scott (INL)

Formulation of the Density Eigenvalue Problem in Neutron Transport for Relevant Engineering Applications

N. Abrate (Politecnico di Torino), S. Dulla (Politecnico di Torino), P. Ravetto (Politecnico di Torino), P. Saracco (INFN)

Development of a High Fidelity Model of the CROCUS Experimental Reactor

Tom Mager (École Polytechnique Fédérale de Lausanne), Mathieu Hursin (Paul Scherrer Institute), Carlo Fiorina (École Polytechnique Fédérale de Lausanne), Andreas Pautz (Paul Scherrer Institute)

Simulation of Neutron Noise in the Research Reactor AKR-2: Comparison Between a Discrete Ordinates and a Diffusion-Based Method

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

Frequency-Domain vs Time-Domain SPN Equations to Simulate Neutron Noise

A. Carreño (Univ. Politècnica de València), A. Vidal-Ferràndiz (Univ. Politècnica de València), D. Ginestar (Univ. Politècnica de València), G. Verdú (Univ. Politècnica de València)

Error Analysis of Numerical Methods for Thick Diffusive Neutron Transport Problems on Shishkin Mesh

Dean Wang (Ohio State)

Setup and Verification of a SCALE/KENO Platform for Generic FHR Benchmark Calculations

Noah A. Walton (Univ. Tennessee, Knoxville), Robert Crowder (Univ. Tennessee, Knoxville), Vladimir Sobes (Univ. Tennessee, Knoxville), Nader Satvat (Kairos Power), Massimiliano Fratoni (Univ. California, Berkeley), Fatih Sarikurt (Kairos Power), Richard Hernandez (Kairos Power)

Zero Power Experiment for Molten Salt Reactor -- Code Verification and Validation Request

A. Detkina (Univ. Liverpool), D. Litskevich (Univ. Liverpool), M. Drury (Univ. Liverpool), B. Merk (Univ. Liverpool)

Impact of Nuclear Data Covariance Libraries on Uncertainty Quantification of Sodium Cooled Fast Reactor Simulation

I. Trivedi (INL), K. Zeng (NCSU), J. Hou (NCSU), N. Stauff (ANL)

Sensitivity Analyses of a Homogeneous Model and a RZ Model of the MYRRHA Reactor in its Critical Configuration

Ciro Alfonso (SCK-CEN), Pablo Romojaro (SCK-CEN), Luca Fiorito (SCK-CEN), Augusto Hernandez-Solis (SCK-CEN)

Evaluating the X2 Initial Core Zero Power Physics Tests with Serpent-Ants

Ville Valtavirta (VTT Technical Research Centre of Finland), Unna Lauranto (VTT Technical Research Centre of Finland), Antti Rintala (VTT Technical Research Centre of Finland)

Feynman-α Analysis Using BGO Gamma-Ray Detector in UTR-KINKI Reactor

Masaki Goto (Kindai Univ.), Tadafumi Sano (Kindai Univ.), Kunihiro Nakajima (Kindai Univ.), Takashi Kanda (Kindai Univ.), Atsushi Sakon (Kindai Univ.), Kengo Hashimoto (Kindai Univ.)

Validation of MPACT BWR Capabilities Against Critical Experiments

Yuxuan Liu (Univ. Michigan), Daniel Jabaay (Univ. Michigan), Brendan Kochunas (Univ. Michigan), Kang Seog Kim (ORNL)

Simulation of SPND Beta-Current in AP1000 Core

Ruizhi Shao (Xi’an Jiaotong Univ.), Liangzhi Cao (Xi’an Jiaotong Univ.), Yunzhao Li (Xi’an Jiaotong Univ.), Fengwei Si (Sanmen Nuclear Power Co.), Tengfei Hao (Sanmen Nuclear Power Co.), Chao Du (Sanmen Nuclear Power Co.), Wan Chenghui (Xi’an Jiaotong Univ.), Wei Shen (Xi'an Jiaotong Univ.)

The Fast Neutron Source at UTK: A Project with Massimo Salvatores

V. Sobes (Univ. Tennessee, Knoxville), J. Pevey (Univ. Tennessee, Knoxville), A. Depillis (Univ. Tennessee, Knoxville), O. Chvala (Univ. Tennessee, Knoxville), S. Bogetic (Univ. Tennessee, Knoxville), W. Hines (Univ. Tennessee, Knoxville)

A Revisitation of the ENEA TAPIRO Fast Source Reactor Neutronic Capabilities.

S. Dulla (Politecnico di Torino), M. Carta (ENEA), N. Burgio (ENEA), V. Fabrizio (ENEA), L. Falconi (ENEA), V. Peluso (ENEA), A. Santagata (ENEA)

A Refined Assessment of Nuclear Data Target Accuracy Requirements for ALFRED

Donato Maurizio Castelluccio (ENEA), Giacomo Grasso (ENEA), Francesco Lodi (ENEA), Vincenzo Peluso (ENEA)

Status of the WPEC Subgroup 46 Efficient and Effective Use of Integral Experiments for Nuclear Data Validation

M. Hursin (Paul Scherrer Institute), O. Cabellos (Univ. Politécnica de Madrid), G. Palmiotti (INL)

Westinghouse Advanced Fuel Management Strategies Leveraging High Enrichment and High Burnup Fuel to Optimize PWR Economics

Ho Lam (Westinghouse Electric Co.), Arielle Konig (Westinghouse Electric Co.), Chris Wagener (Westinghouse Electric Co.), Fausto Franceschini (Westinghouse Electric Co. )

Transition Core Modeling for Extended Enriched, Accident Tolerant Fuel Using PARCS/Polaris

Muhammad Rizki Oktavian (Purdue), Ugur Mertyurek (ORNL), Yunlin Xu (Purdue)

Reactor Physics Benchmark of Westinghouse PWR Core Design Suite for High Burnup/High Enrichment Fuel -- Part I: Pin and Lattice

Fausto Franceschini (Westinghouse Electric Co. ), Gary Mangham (Westinghouse Electric Co.), David Salazar (Westinghouse Electric Co.), Mykola Boychenko (Westinghouse Electric Co.)

Reactor Physics Benchmark of Westinghouse PWR Core Design Suite for High Burnup/High Enrichment Fuel -- Part II: 2D and 3D Core Simulations

Gary Mangham (Westinghouse Electric Co.), Fausto Franceschini (Westinghouse Electric Co. ), David A. Salazar (Westinghouse Electric Co.), Mykola Boychenko (Westinghouse Electric Co.)

PWR Loading Pattern Optimization with Reinforcement Learning

Paul Seurin (MIT), Koroush Shirvan (MIT)

Parallel Simulated Annealing with Embedded Machine Learning and Multifidelity Models for Reactor Core Design

William Gurecky (ORNL), Ben Collins (ORNL), Paul Laiu (ORNL), Tara Pandya (ORNL), Quincy Huhn (TAMU), Dave Kropaczek (ORNL)

Group Structure Selection with Random Forests

Vishnu Nair (LANL), Thomas Saller (LANL), Andrew Till (LANL), Nathan Gibson (LANL)

Extension of the PINN Diffusion Model to k-eigenvalue Problems

Mohamed H. Elhareef (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.)

PN Source Expansion Nodal Method in MPACT for Boiling Water Reactors

Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Precise 3D Reactor Core Calculation Using Spherical Harmonics and Discontinuous Galerkin Finite Element Methods

Kenneth Assogba (CEA), Lahbib Bourhrara (CEA), Igor Zmijarevic (CEA), Grégoire Allaire (Institut Polytechnique de Paris)

The MPN Method: A New Angular Discretization Method Based on Piecewise Polynomial Interface Fluxes

Matteo Falabino (CEA), Daniele Sciannandrone (CEA), Emiliano Masiello (CEA), Jean-François Vidal (CEA)

Investigaton of Methods for Targeted Search of Dominant Higher Modes in Subcritical Systems

Ádám Aranyosy (Budapest Univ. Technology and Economics), Mate Szieberth (Budapest Univ. Technology and Economics)

Analytic Error Analysis of Cross Section Interpolation Methods in Nodal Diffusion Codes-I: Theory

Thomas Folk (Univ. Michigan), Siddhartha Srivastava (Univ. Michigan), Dean Price (Univ. Michigan), Brendan Kochunas (Univ. Michigan), Krishna Garikipati (Univ. Michigan)

Analytic Error Analysis of Cross Section Interpolation Methods in Nodal Diffusion Codes-II: Numerical Results

Thomas Folk (Univ. Michigan), Siddhartha Srivastava (Univ. Michigan), Dean Price (Univ. Michigan), Brendan Kochunas (Univ. Michigan), Krishna Garikipati (Univ. Michigan)

POLCA8 -- Modelling of Cross Section Variations Inside Hexagonal Assemblies

Sten-Orjan Lindahl (Westinghouse Electric Co.), Antonios Mylonakis (Westinghouse Electric Co.)

Sensitivity Analysis of Homogenized Cross Sections in AP1000 Lattices

Dean Price (Univ. Michigan), Thomas Folk (Univ. Michigan), Siddhartha Srivastava (Univ. Michigan), Krishna Garikipati (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Rapid Depletion Analysis of Flowing-Pebble Reactor Systems at Equilibrium Using SCALE

S. E. Skutnik (ORNL), F. Bostelmann (ORNL), W.A. Wieselquist (ORNL)

Hyper-Fidelity Depletion Coupled with Discrete Pebble Motion in Pebble Bed Reactors

Yves Robert (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)

Verification of AGREE and Serpent for the Steady State HTR-10 Benchmark Problems

Kaitlyn Barr (Univ. Michigan), Volkan Seker (Univ. Michigan), Jin Li (Univ. Michigan), Andrew Ward (Univ. Michigan), Thomas Downar (Univ. Michigan)

Transient Convective Delayed Neutron Precursors of 235U for the Molten Salt Reactor Experiment

Kyoung O. Lee (ORNL), Matthew A. Jessee (ORNL), Benjamin S. Collins (ORNL), Zack Taylor (ORNL), Aaron M. Graham (ORNL)

Particle Swarm Optimization for Group Structure Optimization for Radiotherapy Shielding

Oluwadamilola Fasina (LANL), Thomas Saller (LANL)

Calculation of Neutron Flux Spectra of the VVER-1000 Mock-up Shielding Benchmark with Monte Carlo Code MCS Utilizing Mesh-Based Weight Window

Fathurrahman Setiawan (Ulsan Nat'l Institute of Science and Technology), Nhan Nguyen Trong Mai (Ulsan Nat'l Institute of Science and Technology), Yunki Jo (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

An Iron Evaluation Story: From TALYS Model Parameters to Validation on the ASPIS Benchmark with the Monte Carlo Code TRIPOLI-4®

Valeria Raffuzzi (Univ. Cambridge), Jean-Christophe Sublet (IAEA), Cedric Jouanne (CEA), Arjan Koning (IAEA), Dimitri Rochman (PSI)

Benchmarking of ENDF/B-VIII.0 Cross Sections for LWR Ex-Core Transport Applications

Greg A. Fischer (Westinghouse Electric Co. )

Optimization of the Deep Neural Network Parameters for Generating Homogenized Fuel Assembly Data for Nodal Codes

Korawit Saeju (Ulsan Nat'l Institute of Science and Technology), Siarhei Dzianisau (Ulsan Nat'l Institute of Science and Technology), Muhammad Farid Khandaq (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Genetic Algorithm-Based Optimisation of the Few-Group Structure for Lead Fast Reactors Analysis

M. Massone (Karlsruher Institut for Technologie), N. Abrate (Politecnico di Torino), G.F. Nallo (Politecnico di Torino), S. Dulla (Politecnico di Torino), P. Ravetto (Politecnico di Torino), D. Valerio (Politecnico di Torino)

Quantification of Neural Networks Uncertainties with Applications to SAFARI-1 Axial Neutron Flux Profiles

Lesego E. Moloko (South African Nuclear Energy Corp.), Pavel M. Bokov (South African Nuclear Energy Corp.), Xu Wu (NCSU), Kostadin N. Ivanov (NCSU)

The Virtual Test Bed (VTB) Repository: A Library of Multiphysics Reference Reactor Models Using NEAMS Tools

G. Giudicelli (INL), C. Permann (INL), D. Gaston (INL), B. Feng (ANL), A. Abou-Jaoude (INL)

Coupling Coarse-Mesh CFD with Fine-Mesh CFD for Modeling for Molten-Salt Reactors in the Virtual Test Bed (VTB)

M. Tano (INL), R. Freile (TAMU), J. Fang (ANL), A. Abou-Jaoude (INL), D. Shaver (ANL)

Coupled Monte Carlo and Thermal-Hydraulics Modeling of a Prismatic Gas Reactor Fuel Assembly Using Cardinal

A.J. Novak (ANL), D. Andrs (INL), P. Shriwise (ANL), D. Shaver (ANL), P.K. Romano (ANL), E. Merzari (Penn State), P. Keutelian (Radiant Industries)

Initial Study on Cross-Section Generation Requirements for a PBR Equilibrium Core

Javier Ortensi (INL), Paolo Balestra (INL)

Development and Verification of the pyIsoDep Depletion Package for Nuclear Thermal Propulsion Reactors

Matt Krecicki (Georgia Tech), Vigneshwar Manickam (Georgia Tech), Dan Kotlyar (Georgia Tech)

Development of Fast-Running Eighth Core Nodal Solution

Akinori Giho (Westinghouse Electric Co.), Baocheng Zhang (Westinghouse Electric Co.), Byron R. Frank (Westinghouse Electric Co.)

Nuclide Inventory Characterization of EBR-II MOX Fuel Test Pins

John D. Bess (JFoster & Assoc.), Chad L. Pope (Idaho State), Andrew S. Chipman (INL), Colby B. Jensen (INL)

Rossi-α Measurements on a System Consisting of Weapons Grade Plutonium Moderated by Polyethylene

George McKenzie (LANL), Theresa Cutler (LANL), Travis Grove (LANL), Alex McSpaden (LANL), Rene Sanchez (LANL)

Demonstration of MOOSE-Based Griffin Reactor Physics Code for Heterogeneous Lead-Cooled Fast Reactor Analysis

Colin Brennan (Univ. Texas, Austin), Hansol Park (ANL), Emily Shemon (ANL)

MCS Solutions for the TVA Watts Bar Unit 1 Multi-Physics Depletion Benchmark

Muhammad Imron (Ulsan Nat'l Institute of Science and Technology), Tung Dong Cao Nguyen (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

An Influence of Manufacturing Tolerances on Pin-Cell k-infinity of MOX Fuel Using Data from the FUBILA Experiment Program

Fujita Tatsuya (Nuclear Regulation Authority)

Inferring Small-Sample-Reactivity Worth from Oscillation Experiment with Auto-Corrected Local Flux

Paul Ferney (CEA), Romain Boffy (CEA), Guillaume Truchet (CEA), Benoit Geslot (CEA), Jean-Marc Palau (CEA)

Multiphysics FISPACT-II and TENDL-2019 Simulation: Neutron-Induced Damage Metrics

Jean-Christophe Sublet (IAEA), Mark Gilbert (United Kingdom Atomic Energy Authority)

Approach to Nuclear Criticality in IAN-R1 Research Reactor

Jose A. Sarta Fuentes (Pontificia Univ. Javeriana), Luis A. Castiblanco B. (Technology and Nuclear Science)

Development of a High-Fidelity Multi-Cycle Model of the Nuscale Small Modular Reactor Using VERA

Una Baker (Univ. Wisconsin, Madison), Marisol Garrouste (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Gabriel J. Soto (Univ. Wisconsin, Madison), Ben Lindley (Univ. Wisconsin, Madison), Brendan Kochunas (Univ. Michigan)

Sensitivity Analysis of Small Modular Reactor mPower with ATHLET

Heliang Wang (Harbin Engineering Univ.), Xiang Wang (Harbin Engineering Univ.)

Development of keff in the Unfolding Process of the LOTUS Reactor Design

Yantao Luo (Harbin Engineering Univ.), Tian Zhang (Harbin Engineering Univ.), Xiang Wang (Harbin Engineering Univ.)

New Capabilities of the MORET 6 Monte Carlo Neutron Transport Code

W. Monange (IRSN), A. Bardelay (IRSN)

Development of a Three-Dimensional APOLLO3® Neutrons Deterministic Scheme for the CABRI Reactor

Tommy Coissieux (CEA), Julien Politello (CEA), Claire Vaglio-Gaudard (CEA), Timothée Kooyman (CEA), Karim Ammar (CEA)

Coupling TRACE with Nodal Neutronics Code Ants Using the Exterior Communications Interface and VTT's Multi-Physics Driver Cerberus

R. Tuominen (VTT Technical Research Centre of Finland), R. Komu (VTT Technical Research Centre of Finland), V. Valtavirta (VTT Technical Research Centre of Finland)

Comparison and Investigation of Production of Specific Nuclides by Different Fission Yield Data

Ryosuke Shibano (Osaka Univ.), Hirochika Tanaka (Osaka Univ.), Masato Ohara (Osaka Univ.), Satoshi Takeda (Osaka Univ.), Takanori Kitada (Osaka Univ.)

Error Analysis of a Hybrid Control Drum Worth Model

Dean Price (Univ. Michigan), Shai Kinast (Nuclear Research Center Negev), Brendan Kochunas (Univ. Michigan)

Phase I Specifications and Preliminary Sensitivity Analyses of the OECD-NRC Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark

David Holler (NCSU), Maria Avramova (NCSU), Cole Takasugi (NCSU), Rodolfo Vaghetto (TAMU), Yassin Hassan (TAMU)

Thermal Performance Sensitivity to Radial Power Flattening Considerations in Nuclear Thermal Propulsion Reactors

Matt Krecicki (Georgia Tech), Dan Kotlyar (Georgia Tech)

An Economics-By-Design Approach to a Radiant Integrated Thermophotovoltaic Microreactor System

Naiki Kaffezakis (Georgia Tech), Dan Kotlyar (Georgia Tech)

Reactivity Initiated Accident Uncertainty Quantification for Fuel Assembly with Subchannel Code

Awais Zahur (Ulsan Nat'l Institute of Science and Technology), Jinsu Park (Ulsan Nat'l Institute of Science and Technology), Alexey Cherezov (Paul Scherrer Institute), Yunki Jo (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Studsvik R2 Materials Test Reactor Ad Hoc Depletion Strategy for the Derivation of the Fuel Isotopic Composition of the MPCMIV Benchmark

L. Giaccardi (NINE), S. Di Pasquale (NINE), S. Dulla (NINE), M. Cherubini (NINE), A. Petruzzi (NINE)

High-Burnup Isotopics Bias and Uncertainty Estimations for LANCR02

Joshua P. Finch (Global Nuclear Fuel), John Hannah (Global Nuclear Fuel)

Exponential Time Differencing Scheme for Mass Transport and Depletion in Molten Salt Reactors

Zack Taylor (ORNL), Benjamin S. Collins (ORNL), G. Ivan Maldonado (Univ. Tennessee, Knoxville)

An IIPG-Based Finite Element Framework in MOOSE for Modeling Fiber Reinforced Composite Failure Governed by Extrinsic Cohesive Laws

R. Liu (INL), W. Jin (INL), L. Harbour (INL), F. Kong (INL), C. Permann (INL), D. Gaston (INL), R. Podgorney (INL)

Study of Recirculating Liquid Fuel in a 1D Critical Stationary System

Mathis Caprais (Univ. Paris-Saclay), Daniele Tomatis (CEA)

Putting Multipoint Kinetics to the Test: Preliminary Analysis of the MUSE-4 Experiment with APOLLO3

Giorgio Valocchi (CEA), Jean Tommasi (CEA), Jean-François Lebrat (CEA), Frederic Mellier (CEA)

Deterministic Modelling of the SPERT IV Reactor Transients Using the Multi-Physics Capability of WIMS

Thomas Postlethwaite (HMS Sultan), Brendan Tollit (Jacobs), Peter Smith (Jacobs), Alan Charles (Jacobs)

Recent Progress on the APOLLO3® Calculation Scheme for the FLUOLE2 Experiment

Romain Bertonazzi (CEA), Karim Ammar (CEA), Nicolas Gerard-Castaing (CEA), Stéphane Bourganel (CEA)

Historical Review and Proof-of-Concept Future Method Demonstration of Adaptive Mesh Refinement in Nuclear Engineering for Increased Fidelity and Computational Efficiency

Kristin Stolte (TAMU), Pavel Tsvetkov (TAMU)

Analysis of Near-Field and Far-Field Aerosol Dispersion for Microreactors

Rohan Biwalkar (Pittsburgh Technical), Adam Stein (Breakthrough Institute), Sola Talabi (Pittsburgh Technical)

Continuous Removal of Fission Products from Molten-Salt-Fueled Reactors

Rolland Johnson (Muons), Bruce McNamara (PNNL), Thomas J. Roberts (Muons), R. Bruce Vogelaar (Virginia Tech)

Verification of the LOTUS Code with C5G7 Benchmark

Dzianis Litskevich (Univ. Liverpool), Sebastian Davies (Univ. Liverpool), Anna Detkina (Univ. Liverpool), Bruno Merk (Univ. Liverpool)

Modeling of the TRIGA IPR-R1 Research Reactor with the Serpent2/RINNOVO Nodal Core Analysis Package

Wilker Santos (CDTN / CNEN-MG), Petri Forslund Guimarães (GuimaSoft Computing), Daniel Campolina (CDTN / CNEN - MG), Erwin Müller (CompuSim), Graiciany de Paula Barros (CDTN / CNEN-MG), André Campagnole Santos (CDTN / CNEN-MG)

Development of a High-Fidelity Multi-Physics Coupling Between MCNP6.2 and CTF4.0 for VVER Applications

Yesim Kutlu (NCSU), Pascal Rouxelin (NCSU), Maria Avramova (NCSU), Kostadin Ivanov (NCSU)

Neutronics and Thermal-Hydraulics Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor (gFHR)

Jin Li (Univ. Michigan), Shai Kinast (Nuclear Research Center Negev), Volkan Seker (Univ. Michigan), Nader Satvat (Kairos Power), Dan O'Grady (ANL), Rui Hu (ANL), Thomas Downar (Univ. Michigan)

Benchmark Evaluation of One Dimensional Array of HEU Moderated and Reflected by Lucite

Igor Lengar (Jožef Stefan Institute), Domen Kotnik (Jožef Stefan Institute), Luka Snoj (Jožef Stefan Institute), Jesson Hutchinson (LANL), Rene Sanchez (LANL), Travis Grove (LANL)

NucMesh: Nuclear Reactor Geometry Creation and Mesh Generation Module in NEMoSys

Seth Pemberton (Illinois Rocstar), Alessandro Gondolo (Illinois Rocstar)

Alternative Analysis of the MINERVE ZPR Oscillation Experiments

Guy Shtotland (Israel Atomic Energy Commmision), Assaf Kolin (Nuclear Research Center Negev ), Benoit Geslot (CEA), Patrick Blaise (CEA), Nir Kastin (Nuclear Research Center Negev )

Sensitivity and Uncertainty Analysis of PWR Spent Fuel Observables to Operational and Model Parameters

P. Romojaro (SCK CEN), K. Ambrožič (Jožef Stefan Institute), D. Čalič (Jožef Stefan Institute), L. Fiorito (SCK CEN), K. Govers (Federaal Agentschap voor Nucleaire Controle), A. Hernandez-Solis (SCK CEN), B. Kos (Jožef Stefan Institute), P. Schillebeeckx (European Commission), A. Stankovskiy (SCK CEN), G. Žerovnik (Jožef Stefan Institute), M. Kromar (Jožef Stefan Institute)

Thermal Neutron Scattering Cross Sections for Amorphous Carbon

T. Ahmed (NCSU), N.C. Fleming (NCSU), A.I. Hawari (NCSU)

Development of a Point Kinetics Subroutine for Molten Salt Reactors in RELAP5-3D

John R. Ross (Univ. Texas, Austin), Kevin T. Clarno (Univ. Texas, Austin), Kyzer Gerez (Univ. Texas, Austin), Y.J. Choi (INL)

Power Distribution Estimation Method for SMR Using Ex-Core Detectors: Experimental Demonstration by Plural Control Rod Patterns at KUCA

Rei Kimura (Toshiba Energy Systems and Solutions), Tadafumi Sano (Kindai Univ.), Yuki Nakai (Toshiba Energy Systems and Solutions ), Atsushi Sakon (Kindai Univ.), Satoshi Wada (Toshiba Energy Systems and Solutions ), Kunihiro Nakajima (Kindai Univ.), Takashi Kanda (Kindai Univ.), Masaki Goto (Kindai Univ.), Yoshiyuki Takahashi (Kyoto Univ.), Cheol Ho Pyeon (Kyoto Univ.)

Importance of 3-D SN Depletion in Non-Proliferation Using BSOLVE

Meng-Jen Wang (Univ. Utah), Glenn E. Sjoden (Univ. Utah), Tanner W. Hall (Univ. Utah)

Space-Dependent Calculation of the Multiplicity Moments for Shells

Imre Pázsit (Chalmers Univ. of Technology), Victor Dykin (Chalmers Univ. of Technology)

Deployment of the HFIRCON Transport and Depletion Tool for Plutonium-238 Production Studies

D. Chandler (ORNL), C.R. Daily (ORNL)

Development of the MCNP-ORIGEN Activation Automation tool

Roberto E. Fairhurst-Agosta (Univ. Illinois, Urbana-Champaign), Austin L. Carter (INL), Joshua L. Peterson-Droogh (INL)

Adjoint Sensitivity Analysis and Data Assimilation for Verification of Dry Storage Cask Contents

Zi Liang Tan (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge)

Neutronics Modeling of the Pulsed Plasma Rocket Reactor Using Rattlesnake

Jessica Williams (NCSU), Troy Howe (Howe Industries), Jason Hou (NCSU), Kan Ni (NCSU)

Stereolithographic Geometry Model of the IBR-2M Experimental Facility

A. Talamo (ANL), Y. Gohar (ANL), Yu. N. Pepelyshev (Joint Institute for Nuclear Research), A. Vinogradov (Joint Institute for Nuclear Research), A. Bergeron (ANL)

Performance Improvements of the Windowed Multipole Formalism Using a Rational Fraction Approximation of the Faddeeva Function

Benoit Forget (MIT), Jiankai Yu (MIT), Gavin Ridley (MIT)

Design of a Neural Thermal Scattering (NeTS) Module for Hydrogen in Light Water

C.A. Manring (NCSU), A.I. Hawari (NCSU)

A Unified Framework of Stabilized Finite Element Method for Solving the Boltzmann Transport Equation

Liangzhi Cao (Xi’an Jiaotong Univ.), Chao Fang (Xi’an Jiaotong Univ.), Yifei Li (Xi’an Jiaotong Univ.), Qingming He (Xi’an Jiaotong Univ.)

Stability Analysis of Monte Carlo Burnup Calculation Based on PWR Fuel Rods

Ziliang Zeng (Sino-French Institute of Nuclear Engineering and Technology), Adrien Bidaud (CNRS), Davide Portinari (Institut Laue-Langevin)

Statistical Uncertainty of Fission Matrix Eigenvalues Using Perturbation Theory

Constantin Bénilan (Univ. Grenoble Alpes), Adrien Bidaud (Univ. Grenoble Alpes), Thomas Croisette (Univ. Grenoble Alpes), Juliette Martin (Univ. Grenoble Alpes), Laurent Chabert (TechnicAtome), Davide Portinari (Institut Laue-Langevin)

Proposal and Application of ROM-Lasso Method for Sensitivity Coefficient Evaluation

Ryota Katano (Japan Atomic Energy Agency), Akio Yamamoto (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.)

A New Approach for Resonance Treatment of Doubly Heterogeneous Fuel Using the RSE Method

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

Application of Constellation's Best Estimate Alternate Source Term Methodology

J. Massari (Constellation), B. Sarikaya (Constellation), L. Wells (Constellation), S. Gardner (Constellation)

Data Assimilation for Burnup Distribution of PWR with Three-Dimensional Variational Algorithm and Artificial Neutral Network

Lin Guo (Xi’an Jiaotong Univ.), Chenghui Wan (Xi’an Jiaotong Univ.), Hongchun Wu (Xi’an Jiaotong Univ.), Wei Shen (Xi'an Jiaotong Univ.)

Overview of Recent SCALE Activities for Non-LWR Inventory and Decay Heat Analysis

William A. Wieselquist (ORNL), Friederike Bostelmann (ORNL), Robert Kile (ORNL), Austin Lo (ORNL), Ugur Mertyurek (ORNL), Alex Shaw (ORNL), Steve Skutnik (ORNL), Erik Walker (ORNL)

Cell Dancoff-Based Embedded Self-Shielding Capability for Doubly Heterogeneous Particulate Fuels in SCALE/Polaris

Byoung-kyu Jeon (Univ. Michigan), Won Sik Yang (Univ. Michigan), Hansol Park (Univ. Michigan), Kang Seog Kim (ORNL), Matthew A. Jessee (ORNL), William A. Wieselquist (ORNL)

Neutronic Analysis of a PWR-Type SMR Core Using Duplex ThO2-UO2 in TRISO Fuel Particles

Jesús Rosales (Univ. Nacional Autónoma de México), Juan-Luis François (Univ. Nacional Autónoma de México), Carlos García (InSTEC)

Comparative Analysis of Energy Deposition Modes Available in Serpent 2 Within the Framework of the Supercritical Water Reactor -- Fuel Qualification Test Reactor Physics Benchmark

B. Babcsány (Budapest Univ. Technology and Economics), V. Giusti (Univ. Pisa), A. Moise (Institute for Nuclear Research), J. C. Chow (Canadian Nuclear Laboratories)

High-Performance and High-Fidelity Monte Carlo Solutions to the BEAVRS Benchmark

Kyung Min Kim (Seoul Nat'l Univ.), Jaeuk Im (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)

Uncertainty Analysis for VERA Problem #2 Using the Cell-Code Condor v2.8.05

Diego Ferraro (INVAP S.E.), Eduardo Villarino (INVAP S.E.)

Dancoff-Based Wigner-Seitz Approximation for the Subgroup Resonance Self-Shielding in the VERA Neutronics Simulator MPACT

Kang Seog Kim (ORNL), Aaron M. Graham (ORNL), Matthew A. Jessee (ORNL)

Transformational Challenge Reactor Design Characteristics

B.J. Ade (ORNL), B.R. Betzler (ORNL), A.J. Wysocki (ORNL), J.R. Weinmeister (ORNL), N.D. See (ORNL), P.K. Jain (ORNL), W.M. Kirkland (ORNL), J.R. Burns (ORNL), B.D. Hiscox (ORNL), D.P. Schappel (ORNL), A. Talamo (ANL), A. Bergeron (ANL), C.J. Jesse (INL)

Comprehensive Compilations of Computation Results and Validations for Neutronics Start-up Tests at China Experimental Fast Reactor

Jiwon Choe (KAERI), Chirayu Batra (IAEA), Vladimir Kriventsev (IAEA), Armando Gomez-Torres (Instituto Nacional de Investigaciones Nucleares), Alexander Levchenko (Simulation Systems), Batki Balint (Centre for Energy Research), Una Davis (Univ. Cambridge), Jong Hyuck Won (KAERI), Min Jae Lee (KAERI), Pierre Sciora (CEA), Kunhiraman Devan (Indira Gandhi Centre for Atomic Research), Taek K. Kim (ANL), Huo Xingkai (China Institute of Atomic Energy)

Simulation of CEFR Neutronic Start-up Tests with FENNECS

A. Seubert (GRS), Romain Henry (GRS)

TRIPOLI-4® Neutronics Calculations for IAEA-CRP Benchmark of CEFR Start-up Tests Using New Libraries JEFF-3.3 and ENDF/B-VIII

Yi-Kang Lee (CEA)

CEFR Simulation Using Diffusion Code System RAST-F

Tuan Quoc Tran (Ulsan Nat'l Institute of Science and Technology), Tung D.C. Nguyen (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Pellet Cladding Mechanical Interaction as a Potential Failure Mechanism During a Control Rod Drop Accident in a Boiling Water Reactor

Kyle A. Gamble (INL), Aysenur Toptan (INL), Pierre-Clement A. Simon (INL), Aaron Graham (ORNL), Mehdi Asgari (ORNL), Baris Sarikaya (Constellation), James Tusar (Constellation), Moussa Mahgerefteh (Constellation)

Accelerated Coupled Monte Carlo-Thermal Hydraulic Calculations Using a Hybrid GTF-Diffusion-Based Prediction Block: First Results

Bailey Painter (Georgia Tech), Stefano Terlizzi (INL), Dan Kotlyar (Georgia Tech)

On-the-Fly Response Function Generation Method for Composite Coarse Mesh

Dingkang Zhang (Georgia Tech), Farzad Rahnema (Georgia Tech)

Rotational Symmetry Relation for Efficient Response Function Generation in the Coarse Mesh Transport Method COMET

Dingkang Zhang (Georgia Tech), Farzad Rahnema (Georgia Tech)

On the Novel 3-D Neutron Transport Kinetic tRAPID Algorithm and its Validation

Valerio Mascolino (Virginia Tech), Alireza Haghighat (Virginia Tech), Luka Snoj (Jožef Stefan Institute)

An Inline Burn-up Algorithm: Proposal and Preliminary Analysis

P. Cosgrove (Univ. Cambridge), E. Shwageraus (Univ. Cambridge), J. Leppänen (VTT Technical Research Centre of Finland)

Study of Reference Burnup Steps Optimization in Fuel Segment Data File Generation for NEXUS/ANC9 Code System

Baocheng Zhang (Westinghouse Electric Co. ), Mike Gavalek (Westinghouse Electric Co.)

Application of the bRapid Fission Matrix Burnup Methodology to the JSI TRIGA Mark II Research Reactor

Anze Pungercic (Jožef Stefan Institute), Alireza Haghighat (Virginia Tech), Luka Snoj (Jožef Stefan Institute)

An APEC-Corrected 2-D NEM Macroscopic Depletion Analysis of Partial MOX SMRs

Seongdong Jang (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)

Multiscale Thermal Hydraulic Coupling Methods for Boiling Water Reactor Simulation

Aaron Graham (ORNL), Benjamin Collins (ORNL), Bob Salko (ORNL), Mehdi Asgari (ORNL)

VERA BWR Progression Problems

Chase Lawing (NCSU), Scott Palmtag (NCSU), Mehdi Asgari (ORNL)

Preliminary Simulation Results of Peach Bottom Unit 2 Cycles 1 and 2 with MPACT

Sooyoung Choi (Univ. Michigan), Andrew Ward (Univ. Michigan), Aaron Graham (ORNL), Benjamin Collins (ORNL), Brendan Kochunas (Univ. Michigan), Mehdi Asgari (ORNL)

Applicability of Neutronics Design Calculation Method for Axially Heterogeneous Core of RBWR (Resource-Renewable Boiling Water Reactor)

Kimihiro Yokoi (Hitachi-GE Nuclear Energy), Tetsushi Hino (Hitachi-GE Nuclear Energy), Kazuya Ishii (Hitachi-GE Nuclear Energy), Junichi Miwa (Hitachi-GE Nuclear Energy), Hideo Soneda (Hitachi-GE Nuclear Energy), Mikolaj Adam Kowalski (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge), Brendan Kochunas (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Yuxuan Liu (Univ. Michigan), Yasunobu Nagaya (Japan Atomic Energy Agency)

Preliminary Experiment in a Graphite-Moderated Core to Avoid Full Mock-Up Experiment for the Future First Commercial HTGR

S. Okita (Japan Atomic Energy Agency), Y. Fukaya (Japan Atomic Energy Agency), A. Sakon (Kindai Univ.), T. Sano (Kindai Univ.), Y. Takahashi (Kyoto Univ.), H. Unesaki (Kyoto Univ.)

Sockeye Validation Support Using the SPHERE Facility

Joshua Hansel (INL), Jeremy Hartvigsen (INL), Lander Ibarra (ANL), Piyush Sabharwall (INL), Bo Feng (ANL)

Validation of Serpent 2 Depletion Calculations Against Experimental Data from the Advanced Gas Reactor (AGR) Irradiation Campaign

Tatiana Siaraferas (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)

Beta-Ray-Bremsstrahlung Contribution to the Delayed-Photoneutron Group for Heavy Water Reactor

Yanuar Ady Setiawan (Ulsan Nat'l Institute of Science and Technology), Hemantika Sengar (Amity Univ., Noida), Douglas A. Fynan (Ulsan Nat'l Institute of Science and Technology)

Nuclear Data Sensitivity and Uncertainty Analysis on the Neutronics Study of the China Experimental Fast Reactor

Anayochukwu Njoku (SCK-CEN), Augusto Hernandez Solis (SCK-CEN), Luca Fiorito (SCK-CEN), Alexey Stankovskiy (SCK-CEN), Gert Van den Eynde (SCK-CEN), Pablo Romojaro (SCK-CEN)

Evaluation of the Rod Worth Uncertainty from S-Curve for Neutronics Start-Up Tests at China Experimental Fast Reactor

Min Jae Lee (KAERI), Jong Hyuck Won (KAERI), Jiwon Choe (KAERI), Jae-Yong Lim (KAERI)

Self-Shielding Effect on the Calculation of Foil Reaction Rate for CEFR Benchmark

Zhaopeng Zhong (ANL), Michael Jarrett (TerraPower), T.K. Kim (ANL), Changho Lee (ANL)

Analysis of the Reactivity Effects Exercises of the Neutronics Benchmark of the CEFR Start-Up Tests

S. Di Pasquale (NINE), M. Cherubini (NINE), A. Petruzzi (NINE), V. Giusti (Univ. Pisa)

Predicting the Asymptotic State of Reactor Transients Using Supervised Learning

H. Tohver (Univ. Tartu), R. de Oliveira (National Institute of Chemical Physics and Biophysics), J. Pata (National Institute of Chemical Physics and Biophysics), M. Jeltsov (National Institute of Chemical Physics and Biophysics)

Evolution of Fuel Cycle Reload Safety Analysis with Machine Learning -- Illustration on the Rod Ejection Accident

R. Spaggiari (Framatome), M. Segond (Framatome), L. Lefebvre (Framatome)

Using Physics-Informed Neural Networks to Solve a System of Coupled Nonlinear ODEs for a Reactivity Insertion Accident

Alexandra Akins (NCSU), Xu Wu (NCSU)

Improving the Predictivity of a Steam Generator Clogging Numerical Model by Global Sensitivity Analysis and Bayesian Calibration Techniques

L. Lefebvre (Framatome), M. Segond (Framatome), R. Spaggiari (Framatome), L. Le Gratiet (EDF), E. Deri (EDF), B. Iooss (EDF), G. Damblin (CEA)

Monte Carlo Variance Reduction in MOOSE Stochastic Tools Module: Accelerating the Failure Analysis of Nuclear Reactor Technologies

Somayajulu L.N. Dhulipala (INL), Zachary M. Prince (INL), Andrew E. Slaughter (INL), Lynn B. Munday (INL), Wen Jiang (INL), Benjamin W. Spencer (INL), Jason D. Hales (INL)

Towards Multiphysics Simulations of Fusion Breeder Blankets

Helen Brooks (UKAEA), Stephen Dixon (UKAEA), Andrew Davis (UKAEA)

Spectrally-Resolved Electron Transport for Thermal Property Prediction

Jackson R. Harter (INL), Shuxiang Zhou (INL), Sebastian Schunert (INL), Andrea Jokisaari (INL), P. Alex Greaney (Univ. California, Riverside)

Variance Analysis of the Coupling of Thermal-Hydraulics and Point Kinetics with Stochastic Noise Term Modeling Dynamic Monte Carlo Behavior for Later Use in GUARDYAN

Tamás Hajas (Budapest Univ. Technology and Economics), Gábor Tolnai (Budapest Univ. Technology and Economics), Dávid Légrády (Budapest Univ. Technology and Economics)

Improving the Variance in Monte Carlo Criticality Calculations with Adaptive Multilevel Splitting

Kévin Fröhlicher (IRSN), Eric Dumonteil (CEA), Loic Thulliez (CEA), Julien Taforeau (IRSN), Mariya Brovchenko (IRSN)

Monte Carlo Source Convergence Acceleration with Multi-Group Inactive Cycles

Valeria Raffuzzi (Univ. Cambridge), Lee Morgan (AWE), Eugene Shwageraus (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge)

Reactor Period Calculations by Monte Carlo Methods: Analysis of the SPERT III E-Core Reactivity Excursions

R. Hourcade (CEA), A. Jinaphanh (CEA), A. Zoia (CEA)

Hybrid Geometry Modeling of the Alternative Designs of the Bottom Reflector of the 3D Printed Transformational Challenge Reactor

A. Talamo (ANL), A. Bergeron (ANL), S.N.P. Vegendla (ANL), F. Heidet (ANL), B. Ade (ORNL), B.R. Betzler (ORNL)

An Efficient High-To-Low Informing Scheme for Core Neutronics Calculations Based on NEAMS Tools

Kan Ni (NCSU), Jason Hou (NCSU)

Comparison of Two Subgroup Methods Based on the Physical Probability Tables

Emeline Rosier (CEA), Li Mao (CEA), Igor Zmijarevic (CEA), Luiz Leal (IRSN), Richard Sanchez (CEA)

Neutron and Photon Experimental Characterization of Peripheral Irradiation Positions in the CABRI Reactor

T. Kooyman (CEA), O. Clamens (CEA), J. Lecerf (CEA), A. Gruel (CEA), C. Vaglio-Gaudard (CEA)

LEU+ BWR Lattice Design Optimization of Using SCALE/Polaris

Jin Whan Bae (ORNL), Ugur Mertyurek (ORNL), Mehdi Asgari (ORNL)

Development of Cross-Section Data Set Repository and Interpolation Code System, LOCUS

Michael Gavalek (Westinghouse Electric Co.), Akinori Giho (Westinghouse Electric Co.), Ho Q. Lam (Westinghouse Electric Co.), Baocheng Zhang (Westinghouse Electric Co.)

Verification of SIMULATE5 Pin Powers for Large Assembly Bow

Joshua Hykes (Studsvik Scandpower), Tamer Bahadir (Studsvik Scandpower)

NEWT Lattice Physics Code Bias Analysis and Compensation Strategy for Pressurized Water Reactor Calculations

L. Durán-Vinuesa (Univ. Politécnica de Madrid), D. Cuervo (Univ. Politécnica de Madrid), N. Garcia-Herranz (Univ. Politécnica de Madrid)

Calculation Methods of B4C Control Rod Curves in a Fast VENUS-F Reactor

N. Messaoudi (SCK-CEN), A. Kochetkov (SCK-CEN), A. Krasa (SCK-CEN), G. Vittiglio (SCK-CEN), J. Wagemans (SCK-CEN), G. Van den Eynde (SCK-CEN), M. Sarotto (ENEA), V. Fabrizio (ENEA)

Millimetric Fuel Rod Displacements: An Experimental Study of the Impact on Local Thermal Neutron Flux in the CROCUS Reactor

F. Vitullo (École Polytechnique Fédérale de Lausanne), V. Lamirand (École Polytechnique Fédérale de Lausanne), T. Ligonnet (École Polytechnique Fédérale de Lausanne), O. Pakari (École Polytechnique Fédérale de Lausanne), D. Godat (École Polytechnique Fédérale de Lausanne), P. Frajtag (École Polytechnique Fédérale de Lausanne), A. Pautz (École Polytechnique Fédérale de Lausanne)

Research and Preliminary Application of the Improved Multicell Method for the PWR Fuel Assemblies Adjacent to the Baffle Reflector

Chenghui Wan (Xi’an Jiaotong Univ.), Wenchang Dong (Xi’an Jiaotong Univ.), Wei Shen (CANDU Owner Group), Hongchun Wu (Xi’an Jiaotong Univ.)

Horizontal Split Table Conceptual Design for Advanced Reactor Validation

Mathieu N. Dupont (ORNL), Justin B. Clarity (ORNL), Daniel J. Siefman (LLNL), Catherine M. Percher (LLNL)

Expanded Validation of Uranium Systems with the KENO Monte Carlo Codes and SCALE 6.2.4

W.J. Marshall (ORNL), O.M. Belcher (US Naval Academy), N.H. Byrne (US Naval Academy), L.E. de Leon (US Naval Academy), M.N. Solis (US Naval Academy), T.M. Greene (ORNL), S.R. Blair (US Naval Academy)

Uncertainty Quantification in Neutron Noise Analysis Using Monte-Carlo Markov Chain Methods: An Application to Nuclear Waste Drum Assay

Paul Lartaud (CEA), Philippe Humbert (CEA), Josselin Garnier (CMAP)

Benchmark of Neutron Thermalization in Graphite Using a Pulsed Slowing-Down-Time Experiment

E. Lee (NCSU), N.C. Fleming (NCSU), A.I. Hawari (NCSU)

RAST-AI: A Standalone Nodal Diffusion/Deep Neural Network Code for Reactor Analysis and Simulation

Siarhei Dzianisau (Ulsan Nat'l Institute of Science and Technology), Fathurrahman Setiawan (Ulsan Nat'l Institute of Science and Technology), Korawit Saeju (Ulsan Nat'l Institute of Science and Technology), Jinsu Park (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Using Neural Networks to Predict Pin Powers in Reflective PWR Fuel Assemblies with Varying Pin Size

Aidan Furlong (Univ. Florida), Forrest Shriver (Sentinel Devices), Justin Watson (Univ. Florida)

Prediction of Nuclear Reactor Core Parameters Using Artificial Neural Network

Wojciech Kubinski (National Centre for Nuclear Research), Piotr Darnowski (Warsaw Univ. Technology), Krzysztof Palmi (Warsaw Univ. Technology)

Speed Up of Partial Current Tallies in SERPENT

Oscar Lastres (Purdue), Yunlin Xu (Purdue)

Toward Portable GPU Acceleration of the OpenMC Monte Carlo Particle Transport Code

John R. Tramm (ANL), Paul K. Romano (ANL), Johannes Doerfert (ANL), Amanda L. Lund (ANL), Patrick C. Shriwise (ANL), Andrew R. Siegel (ANL), Gavin Ridley (MIT), Andrew Pastrello (Univ. New South Wales)

Development of an Optimum Detector Position Search Method for Pulsed-Neutron-Source Alpha Measurement Using Time-Dependent Monte Carlo Simulation

S. H. Jang (Seoul Nat'l Univ.), H. J. Shim (Seoul Nat'l Univ.)

Performance of Population Control Techniques in Monte Carlo Reactor Criticality Simulation

Ilham Variansyah (Univ. Notre Dame), Ryan G. McClarren (Univ. Notre Dame)

Comparison of CASMO-5, MPACT and Serpent 2 for the Modeling of Advanced BWR Lattices

M. Hursin (Paul Scherrer Institute), P. Mala (Paul Scherrer Institute), A. Vasiliev (Paul Scherrer Institute), H. Ferroukhi (Paul Scherrer Institute), Yuxuan Liu (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan)

Demonstration of an Embedded Diffusion Scheme for Modelling the BEAVRS Benchmark Problem

R. H. Prinsloo (Necsa), S.A. Groenewald (Necsa), C. Jacobs (Necsa), D.I. Tomašević (Necsa), Kostadin Ivanov (NCSU)

Development and Validation of the GNF Core Simulator Package LANCR02/PANAC11 for the Evaluation of Boiling Water Reactors with LEU+ and High Burn-up Fuel Characteristics

J. Hannah (Global Nuclear Fuel), K. Bennett (Global Nuclear Fuel), G. Cuevas-Vivas (Global Nuclear Fuel), J. Finch (Global Nuclear Fuel), F. Jones (Global Nuclear Fuel), L. Pogosbekyan (Global Nuclear Fuel), B. Ward (Global Nuclear Fuel)

Fuel Cycle Depletion to Spent Fuel Gamma Facility Dose Rate Validation Studies

D. Chandler (ORNL)

Thermal Neutron Scattering Law Evaluations for Zirconium Carbide and Critical Mass Calculations

J.L. Wormald (Naval Nuclear Laboratory), J.C. Holmes (Naval Nuclear Laboratory), M.L. Zerkle (Naval Nuclear Laboratory)

Spectral Indices Measurements for Neutron Data Validation in the Lead - Bismuth VENUS-F Fast Cores for MYRRHA

A. Kochetkov (SCK-CEN), A. Krása (SCK-CEN), N. Messaoudi (SCK-CEN), G. Vittiglio (SCK-CEN), J. Wagemans (SCK-CEN)

Measurement of U-233 Sample Reactivity Worth in KUCA for Integral Validation of Nuclear Data

Tadafumi Sano (Kindai Univ.), Jun-ichi Hori (Kyoto Univ.), Yoshiyuki Takahashi (Kyoto Univ.), Kazushi Terada (Kyoto Univ.), Hiroshi Yashima (Kyoto Univ.), Takashi Kanda (Kindai Univ.), Hironobu Unesaki (Kyoto Univ.)

Development of a Model to Estimate Resuspension of Fission Products in an Integral Pressurized Water Reactor Containment Vessel

Rohan Biwalkar (Pittsburgh Technical), Iza Lantgios (Univ. Pittsburgh), Sola Talabi (Pittsburgh Technical), Katherine Hornbostel (Univ. Pittsburgh)

Modeling and Analysis of a Micro-Reactor Using the DireWolf Code Suite

Nathan Roskoff (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Alex Levinsky (Westinghouse Electric Co.), Vincent Laboure (INL), Jackson Harter (INL), Adam Zabriskie (INL), Lise Charlot (INL)

Simulation of a TRISO-Fueled Heat-Pipe Microreactor Using MOOSE-Based Reactor Physics Code Griffin

Yan Cao (ANL), Nicolas Stauff (ANL), Yinbin Miao (ANL), Kun Mo (ANL), Justin Thomas (ANL), Bo Feng (ANL), Zhaopeng Zhong (ANL), Chang-ho Lee (ANL)

Preliminary Neutronic-Thermal-Mechanical Coupling of a Small Heat-Pipe Reactor Using OpenMC and MOOSE

William Reed Kendrick (MIT), Benoit Forget (MIT)

Design, Simulation, and Analysis of a Microreactor Experiment at the National Criticality Experiments Research Center

Mikaela Blood (LANL), Alexis Maldonado (LANL), Nicholas Thompson (LANL), Holly Trellue (LANL)

Recent Developments in the OpenMC Monte Carlo Particle Transport Code

Paul K. Romano (ANL), Patrick C. Shriwise (ANL), Sterling M. Harper (TerraPower), Andrew E. Johnson (Ultra Safe Nuclear Corp.), Amanda L. Lund (ANL), Jingang Liang (Tsinghua Univ.), John R. Tramm (ANL), Andrew Davis (Culham Centre for Fusion Energy), Daniel Short (Culham Centre for Fusion Energy), Younghui Park (Univ. Wisconsin, Madison)

Automatic Conversion of MCNP Geometries to TRIPOLI-4®

Davide Mancusi (CEA)

Verification of OpenMC Neutronic Code for Transuranic Waste Incineration in Reduced Moderation Boiling Water Reactor

Sivakorn Sansawas (King Mongkut's Univ. Technology Thonburi), Saksorn Ruangtanusak (King Mongkut's Univ. Technology Thonburi), Yanin Sukjai (King Mongkut's Univ. Technology Thonburi)

Pre-Release Validation Database for the Multi-Dimensional Fuel Performance Code OFFBEAT

A. Scolaro (École Polytechnique Fédérale de Lausanne), C. Fiorina (École Polytechnique Fédérale de Lausanne), I. Clifford (Paul Scherrer Institute), E. Brunetto (École polytechnique fédérale de Lausanne), A. Pautz (Paul Scherrer Institute)

Assessment of Skyshine in DEMO Using ADVANTG Code

Domen Kotnik (Jožef Stefan Institute), Bor Kos (ORNL), Igor Lengar (Jožef Stefan Institute), Aljaž Čufar (Jožef Stefan Institute), Christian Bachmann (Eurofusion PMU), Luka Snoj (Jožef Stefan Institute)

Shutdown Dose Rate Calculations of JET Using ORCS (ORNL R2S Code Suite)

Bor Kos (ORNL), Georgeta Radulescu (ORNL), Robert Grove (ORNL), Rosaria Villari (ENEA), Paola Batistoni (ENEA), JET Contributors (EUROfusion)

Neutron Flux Distributions for ITER B1 Port Cell 16 Shielding Design

Kara Godsey (ORNL), Bor Kos (ORNL), Matthew Swinney (ORNL)

Nuclear Data Uncertainty Quantification in the ARC Fusion Reactor

Alex Aimetta (Politecnico di Torino), Nicolò Abrate (Politecnico di Torino), Sandra Dulla (Politecnico di Torino), Antonio Froio (Politecnico di Torino)

Reduced Order Modeling of Neutron Transport Using Monte Carlo Simulations with Matrix Sketching

Christophe Murphy (Jacobs), David P. Griesheimer (Naval Nuclear Laboratory)

Alpha-Eigenvalue Monte Carlo Neutron Transport Calculations with SCONE

Saad Islam (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge), Valeria Raffuzzi (Univ. Cambridge)

A Programmatic Metamodel-Driven Modeling Paradigm for MCNP

Peter J. Kowal (Rensselaer Polytechnic Institute), Camden E. Blake (Rensselaer Polytechnic Institute), Kurt A. Dominesey (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)

A Monte Carlo Transient Multilevel Implementation Applied to the C5G7-TD3 Benchmark

Evan S. Gonzalez (Univ. Michigan), Brian C. Kiedrowski (Univ. Michigan)

A 3 Regions Model for LWR Fuel Pin Sensitivity Analysis with Depletion Perturbation Theory

Davide Portinari (Institut Laue Langevin), Yoann Calzavara (Institut Laue Langevin), Laurent Chabert (TechnicAtome), Adrien Bidaud (LPSC-IN2P3-CNRS)

Estimation of Recoverable Energies in Neutron-Induced Fission and Capture with Associated Uncertainties

Kingsley Ogujiuba (NCSU), Gregory Delipei (NCSU), Ugur Mertyurek (ORNL), Jason Hou (NCSU), William Wieselquist (ORNL), Kostadin Ivanov (NCSU)

The Effects Study of Nuclide-Number-Density Distribution on Response Function and DRWM Results

Jiahe Bai (Xi’an Jiaotong Univ.), Chenghui Wan (Xi’an Jiaotong Univ.), Yunzhao Li (Xi’an Jiaotong Univ.), Hongchun Wu (Xi’an Jiaotong Univ.), Wei Shen (Xi'an Jiaotong Univ.)

Comparison of Nodal Numerical Adjoints from Various CMFD-Based Acceleration Schemes

Taesuk Oh (KAIST), Yonghee Kim (KAIST)

Study of Neutronic Phenomenology of Heterogeneous Moderator Voiding in a Partially MOX-Loaded PWR

Sébastien De Mattei (CEA), Géraud Prulhière (CEA), Guillaume Martin (CEA), Jean-François Vidal (CEA)

KONVOI Core Analysis with CASMO5 and SIMULATE5

Emiliya L. Georgieva (Studsvik Scandpower), Marcus Seidl (PreussenElektra), Gerd Anton (Studsvik Scandpower)

Comparative Neutronic Analysis of an Accident Tolerant Fuel Loaded PWR by STREAM/RAST-K

Yunki Jo (Ulsan Nat'l Institute of Science and Technology), Deokjung Lee (Ulsan Nat'l Institute of Science and Technology)

Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels

B. R. Betzler (ORNL), J. Bae (ORNL), D. Chandler (ORNL), G. Ilas (ORNL), E. E. Davidson (ORNL)

Validation of an SMR Gadolinia Burnable Absorber Loading Design with No-Onsite Refueling and Penalty-Free Reactivity

Gray Chang (JFoster & Assoc.), Julie Foster (JFoster & Assoc.), Jim Harrell (Zachry Nuclear), Mie Hiruta (JFoster & Assoc.)

Assessment of Griffin Cross-Section Interpolation Capability on TRISO-Fueled Heat-Pipe Micro-Reactor

Kan Ni (NCSU), Yan Cao (ANL), Nicolas Stauff (ANL), Jason Hou (NCSU)

MCNP and Whisper Neutronics Framework for Designing Microreactor Experiments

Alexis Maldonado (LANL), Christopher M. Perfetti (Univ. New Mexico), Holly Trellue (LANL)

Preliminary Assessment of As-Built Design Characteristics for the Transformational Challenge Reactor

B.J. Ade (ORNL), E. Biondo (ORNL), D.P. Schappel (ORNL), E. Fountain (ORNL), B.R. Betzler (ORNL), G. Davidson (ORNL)

Development of an OpenFOAM Multiphysics Solver for Solid Fission Products Transport in the Molten Salt Fast Reactor

Andrea Di Ronco (Politecnico di Milano), Stefano Lorenzi (Politecnico di Milano), Francesca Giacobbo (Politecnico di Milano), Carolina Introini (Politecnico di Milano), Antonio Cammi (Politecnico di Milano)

The GeN-Foam Multiphysics Solver: A Status Update

C. Fiorina (École Polytechnique Fédérale de Lausanne)

PyARC -- A User-Friendly Open-Source Reactor Physics Framework for Fast Reactor Design and Analysis

N.E. Stauff (ANL), A. Abdelhameed (ANL), M. Atz (ANL), P. Shriwise (ANL), Y.S. Jung (ANL), R. Lefebvre (ORNL)

julia for Enhancing Nuclear Engineering Simulations (JENES): Introduction to the JENES Project and Platform

Muhammad Ramzy Altahhan (NCSU), Gregory Delipei (NCSU), David Holler (NCSU), Jason Hou (NCSU), Maria Avramova (NCSU), Kostadin Ivanov (NCSU)

Demonstration of MCNP and Abaqus Based Reactor Multiphysics (MARM) M&S Framework for Space Nuclear Systems

Vedant K. Mehta (LANL)

Methodology and Preliminary Results for the Transient Control of Pressure and Temperature for Nuclear Thermal Propulsion Engines

Vigneshwar Manickam (Georgia Tech), Matthew Krecicki (Georgia Tech), Dan Kotlyar (Georgia Tech)

Thermo-Mechanics Feedback for Nuclear Thermal Propulsion Analysis: Implementation and Application

Connor Koelsch (Georgia Tech), Sam Heflin (Georgia Tech), Matt Krecicki (Georgia Tech), Dan Kotlyar (Georgia Tech)

Suppressing the Positive Temperature Reactivity Coefficient in Metal Hydride Moderated Reactor

Vedant K. Mehta (LANL), Dasari V. Rao (LANL)

Monte Carlo Depletion with the iDTMC Method in a Small Modular Reactor

Inhyung Kim (KAIST), Inyup Kim (KAIST), Yonghee Kim (KAIST)

Depletion Perturbation Theory Sensitivity Coefficients in Monte Carlo Simulations

Benjamin Murphy (Univ. New Mexico), Christopher Perfetti (Univ. New Mexico)

Layered CAD/CSG Geometry for Neutronics Modeling of Advanced Reactors

Elliott Biondo (ORNL), Gregory Davidson (ORNL), Brian Ade (ORNL)

A Preliminary Design of High Dominance Ratio Configurations for Space-Time Effect Measurements in ZPR : A Tentative Application in VENUS-F

Kornilios Routsonis (NRG), Patrick Blaise (CEA), Jean Tommasi (CEA)

Impact of Infinite Lattice Approximation on Nuclear Safety Evaluation Due to Different Fuel Assembly Loading and Core Configurations

Sebastien Bonthoux (IRSN), Julien Taforeau (IRSN)

Westinghouse Simplified RAVE™ Approach to PWR OT∆T/OP∆T Event Analyses

Peter A. Hilton (Westinghouse Electric Co.), Yixing Sung (Westinghouse Electric Co.), Bedirhan Akdeniz (Westinghouse Electric Co.), Scott Snider (Westinghouse Electric Co.), David A. Salazar (Westinghouse Electric Co.), Michael Gavalek (Westinghouse Electric Co.)

On the Modelling of Fuel Assembly Vibrations Using Coarse Mesh Approaches

C. Demaziere (Chalmers Univ. of Technology)

Load Follow Simulations for the LDR-50 District Heating Reactor Using the Kraken Computational Framework

Jaakko Leppänen (VTT Technical Research Centre of Finland), Ville Valtavirta (VTT Technical Research Centre of Finland), Rebekka Komu (VTT Technical Research Centre of Finland)

Active and Passive Load-Follow Operations in the Soluble-Boron-Free SMR ATOM

Yunseok Jeong (KAIST), Taesuk Oh (KAIST), Nguyen Xuan Ha (KAIST), Yonghee Kim (KAIST)

Coupling of the Secondary Loop and the Cooling Circuit in a PWR Involved in Load Follow Operations

Baptiste Gasse (CEA), Jean-Michel Do (CEA), Hubert Grard (CEA), Cheikh Diop (CEA), Sébastien Verel (Univ. Littoral Côte d’Opale)

X2 VVER-1000 Benchmark Fresh Core Analysis with HELIOS / DYN3D

Matias Zilly (Framatome)

A Comparison of Random Sampling and Genetic Optimization in a Multi-Reactor Shared Fuel Pool Power Plant

Ben Lilley (Oregon State), Todd S. Palmer (Oregon State)

Fuel Loading Pattern Optimization of Allegro Fast Reactor Using Genetic Algorithms

Yrobel Lima-Reinaldo (Univ. Nacional Autónoma de México), Juan-Luis François (Univ. Nacional Autónoma de México)

Evaluation of Fuel Assemblies for Plutonium Multi-Recycling in Pressurised Water Reactors with MOX Enriched Uranium Support Fuel

P. Servell (EDF), E. Girardi (EDF), G. Martin (CEA)

Intra-Optimisation Objective Expansion Applied to Nuclear Fuel Design and Investigation of its Effects on Search Space Coverage

D.J. Brennan (Univ. Cambridge), G.T. Parks (Univ. Cambridge)

Area Ratio Method Using Dynamic Mode Decomposition

Tomohiro Endo (Nagoya Univ.), Fuga Nishioka (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Masao Yamanaka (Kyoto Univ.), Cheol Ho Pyeon (Kyoto Univ.)

Study of Reactor Core Loading Monitoring Within the SALMON Program

A. Bailly (Normandie Univ.), J.-L. Lecouey (Normandie Univ.), A. Billebaud (Univ. Grenoble Alpes), S. Chabod (Univ. Grenoble Alpes), A. Kochetkov (SCK·CEN), A. Krása (SCK·CEN), F.-R. Lecolley (Normandie Univ.), G. Lehaut (Normandie Univ.), N. Marie (Normandie Univ.), N. Messaoudi (SCK·CEN), G. Vittiglio (SCK·CEN), J. Wagemans (SCK·CEN)

Deep Sub-Criticality Determination Using the Source Jerk Integral Method in the SALMON Program

A. Kochetkov (SCK-CEN), A. Krása (SCK-CEN), N. Messaoudi (SCK-CEN), G. Vttiglio (SCK-CEN), J. Wagemans (SCK-CEN), A. Bailly (Normandie Univ.), A. Billebaud (Univ. Grenoble-Alpes), S. Chabod (Univ. Grenoble-Alpes), F.-R. Lecolley (Normandie Univ.), J.-L. Lecouey (Normandie Univ.), G. Lehaut (Normandie Univ.), N. Marie (Normandie Univ.)

Evaluation of Critical Experimental Core Configurations to Simulate Non-Uniform Fuel Debris

Satoshi Gunji (Japan Atomic Energy Agency), Shouhei Araki (Japan Atomic Energy Agency), Kenya Suyama (Japan Atomic Energy Agency), Kazuhiko Izawa (Japan Atomic Energy Agency)

Study and Design of a Molten Salt Reactor for Power Supply in Space: First Glimpse of the Core Design

Nicolas Rey-Tornero (CEA), Guillaume Campioni (CEA), Daniel Heuer (Centre National de la Recherche Scientifique)

Design Studies of a Molten Salt Reactor for Space Nuclear Electric Propulsion

F. Quinteros (Univ. Grenoble Alpes), P. Rubiolo (Univ. Grenoble Alpes), V. Ghetta (Univ. Grenoble Alpes), J. Giraud (Univ. Grenoble Alpes), N. Capellan (Univ. Grenoble Alpes)

Parametric Neutronic Evaluation of the Centrifugal Nuclear Thermal Rocket Concept

William J. Walters (Penn State)

Low Enriched Uranium Particle Bed Rocket

Alejandra de Lara (Univ. Cambridge), Nathaniel Read (Univ. Cambridge)

Effective Kinetic Parameter Estimation in MONK Using an Iterated Fission Probability Method with Superhistory Powering

Andrew Cox (Jacobs), Simon Richards (Jacobs), Geoff Dobson (Jacobs), Paul Smith (Jacobs)

Production of Long-Lived Delayed-Photoneutron Precursors from Activated-Sodium Adjuster Rod in CANDU-6

Yeseul Seo (Ulsan Nat'l Institute of Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute of Science and Technology), Yanuar Ady Setiawan (Ulsan Nat'l Institute of Science and Technology)

Pin-by-Pin Neutronics Simulation of a Hypothetical Control Rod Ejection in a Full VVER-440 Core Using the GUARDYAN Dynamic Monte Carlo Code

E. Pazman (Budapest Univ. Technology and Economics), G. Tolnai (Budapest Univ. Technology and Economics), D. Legrady (Budapest Univ. Technology and Economics), Boglárka Babcsány (Budapest University of Technology and Economics)

Acceleration of Source Convergence in Monte Carlo Criticality Calculation with CMFD Schemes

Firas Abdullatif (Ohio State), Dean Wang (Ohio State)

Boundary Condition Free Homogenization and Evaluation of its Performance in Fast Reactor Core Analysis

Shuhei Maruyama (Japan Atomic Energy Agency)

Flux Flattening Heavy Water Reactors with Accelerator-Driven Photoneutron Source

Arief Rahman Hakim (Ulsan Nat'l Institute of Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute of Science and Technology)

Enhancement Concept Reactor Physics Studies to Support HFIR Upgrade Planning Activities

D. Chandler (ORNL), C.D. Bryan (ORNL), J. L. McDuffee (ORNL)

Depletion Perturbation Theory: A Sensitivity Tool for the High Flux Reactor Conversion to Low Enriched Uranium

Davide Portinari (Institut Laue Langevin), Yoann Calzavara (Institute Laue Langevin), Laurent Chabert (TechnicAtome), Adrien Bidaud (LPSC-IN2P3-CNRS)

Planning for Nuclear Testing After Core Internals Changeout #6 in the Advanced Test Reactor

Nathan Manwaring (INL), Daren Norman (INL)

Uncertainty Calculations with OpenMOC for Lattice Reactor Physics

Mohammad Hashemi (Technical Univ. Munich), R. Reifarth (Goethe Univ. Frankfurt), R. Macian-Juan (Technical Univ. of Munich), A. Hernandez-Solis (SCK-CEN), Pablo Romojaro (SCK-CEN)

Investigation of Approximations in Modeling BWR Void Distributions

Chase Lawing (NCSU), Scott Palmtag (NCSU)

Comparison of LWR Decay Heat Calculations Using ANSI/ANS-5.1-2014 Standard and SCALE

Joseph R. Burns (ORNL), Germina Ilas (ORNL), Ugur Mertyurek (ORNL), William Wieselquist (ORNL)

Criticality Analysis of a Variant Model of a Spent Fuel Cask

Loretta Boahemaa Manu (Harbin Engineering Univ.), Xiang Wang (Harbin Engineering Univ.)

Scoping Studies of Subcritical Minor Actinide-Burning Fission-Fusion Hybrid Designs for Nuclear Waste Reduction

J. Ruegsegger (Univ. Wisconsin, Madison), C. Moreno (Univ. Wisconsin, Madison), M. Nyberg (Univ. Wisconsin, Madison), T. Bohm (Univ. Wisconsin, Madison), P. Wilson (Univ. Wisconsin, Madison), B. Lindley (Univ. Wisconsin, Madison)

Markov Chain Models of Nuclear Transmutation: Theory and Application

Máté Halász (Budapest Univ. Technology and Economics), Mate Szieberth (Budapest Univ. Technology and Economics)

A Novel Approach Towards Criticality Safety of Assemblies with Missing Fuel Rods

Benjamin Dechenaux (IRSN)

State of the Art on Doppler Broadening: Modern Developments on the Fuel-Temperature Coefficient

David Friant (CEA), David Bernard (CEA), Patrick Blaise (CEA)

Importance of the Axial Burn-Up Modelling for Fuel Assembly Nozzles Activation Calculation

Mariya Brovchenko (IRSN), Nadege Kodratoff (IRSN)

APOLLO3(R) Calculation of BWR Fuel Assembly of a Burn-Up Credit Criticality Benchmark

Arthur Le Bars (CEA), Daniele Tomatis (CEA), Igor Zmijarevic (CEA)

Bayesian Inverse Uncertainty Quantification of TRACE Physical Model Parameters Using FEBA Reflood Experiments

Ziyu Xie (NCSU), Xu Wu (NCSU)

Bayesian Data Assimilation for Fuel Performance Based on OFFBEAT

C. Fiorina (École Polytechnique Fédérale de Lausanne), A. Scolaro (École Polytechnique Fédérale de Lausanne), D. Siefman (LLNL), M. Hursin (Paul Scherrer Institute), A. Pautz (Paul Scherrer Institute)

Hierarchical Interpolation of Homogenized Few-Group Neutron Cross-Sections on Samples with Uncorrelated Uncertainty

P.M. Bokov (South African Nuclear Energy Corp.), D. Botes (South African Nuclear Energy Corp.), Kostadin N. Ivanov (NCSU)