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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
Full Issue
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Page 0
Improvements to the MOOSE Reactor Geometry Mesh Builder to Streamline Mesh Generation Workflows for Advanced Reactor Designs
Shikhar Kumar (ANL), Logan Harbour (INL), Guillaume Giudicelli (INL), Yinbin Miao (ANL), Yeon Sang Jung (ANL), Emily Shemon (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 6-15
Fundamental Improvements to the MOOSE Reactor Module and Mesh System for Meshing Advanced Reactor Geometries
Yinbin Miao (ANL), Aaron Oaks (ANL), Guillaume Giudicelli (INL), Roy Stogner (INL), Soon Kyu Lee (ANL), Yeon Sang Jung (ANL), Shikhar Kumar (ANL), Emily Shemon (ANL), Kun Mo (ANL), Logan Harbour (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 16-25
Neutronics Analysis of a Lead-cooled Fast Reactor Using Griffin
Zachary D. Bevans (NCSU), Javier Ortensi (INL), Scott P. Palmtag (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 26-35
APOLLO3-SCRAP Calculation Route for Solid-Fuel Fast Reactors Design Application
Jean-Francois Vidal (CEA), Maciej Zajaczkowski (CEA), Laurent Buiron (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 36-45
Cross Sections Generation and SPH Correction Methods for Deterministic Code Simulation of the Westinghouse LFR Design
Christian Vita (Politecnico di Torino), Nicolo' Abrate (Politecnico di Torino), Sandra Dulla (Politecnico di Torino), Fausto Franceschini (Westinghouse Electric Co.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 48-57
Application of Nodal Numerical Adjoints for Kinetic Parameters Assessment in Two-Step Nodal Code KANT
Taesuk Oh (KAIST), Dongju Choi (KAIST), Yonghee Kim (KAIST)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 58-67
LDR Lite Benchmark Core Analysis Exercise with CASMO5 and SIMULATE5
Emiliya L. Georgieva (Studsvik Scandpower), Tamer Bahadir (Studsvik Scandpower)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 68-77
Mini-Reactor Once-Through Operation Cycle High-Burnup Fuel Depletion Performance Impacts Verification
Gray S. Chang (JFoster & Assoc.), John D. Bess (JFoster & Assoc.), Patrick Moo (JFoster & Assoc.), Julie Foster (JFoster & Assoc.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 78-87
A Computationally Tractable Model for Spatially Resolved Nuclide Concentrations in Flowing Fuel Molten Salt Reactors
Luke Seifert (Univ. Illinois, Urbana-Champaign), Shayan Shahbazi (ANL), Scott Richards (ANL), Madicken Munk (Univ. Illinois, Urbana-Champaign), Kathryn Huff (Univ. Illinois, Urbana-Champaign)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 92-101
Role of Recirculation in Reactivity Loss in Circulating-Fuel Reactors
Lubomir Bures (Seaborg Technologies)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 102-111
Low Resolution Simulation of the Massachusetts Institute of Technology Molten Salt Irradiation Flow Loop
Seth Dayawansa (Univ. Texas, Austin), Kevin T. Clarno (Univ. Texas, Austin), David Carpenter (MIT), Charles Forsberg (MIT)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 112-121
Modeling Continuous Online Refueling with SCALE 6.3.1 and Serpent-2 in the EIRENE Novel Molten Salt Reactor Design
C. Erika Moss (Univ. Tennessee, Knoxville), Ondrej Chvala (Univ. Texas, Austin), Donny Hartanto (ORNL), John P. Carter (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 122-131
A Direct Forcing Immersed Boundary Technique Developed in the NekRS Spectral Element CFD Solver
Aya Hegazy (Univ. Illinois, Urbana-Champaign), April Novak (Univ. Illinois, Urbana-Champaign), Rizwan Uddin (Univ. Illinois, Urbana-Champaign)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 138-147
Thermal Feedback Models for Microreactor Core Simulations
Benjamin Collins (Veracity Nuclear), Micah Best (Veracity Nuclear), Aaron Graham (Veracity Nuclear)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 148-156
Analysis of Fluid Flow Benchmarks for Single-Phase Liquids Using SyTH
Austin Skiba (Univ. Texas, Austin), Nicholas Herring (Univ. Texas, Austin), Caleb Miller (Univ. Texas, Austin), Benjamin Collins (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 157-166
Implementation and Analysis of Delayed Neutron and Decay Heat Precursor Transport in the SyTH Model for Molten Salt Reactor Applications
Braden Pecora (Univ. Texas, Austin), Benjamin S. Collins (Univ. Texas, Austin), Cole Gentry (Univ. Texas, Austin), Nicholas Herring (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 167-175
Examining Xe-Induced Oscillations in Monte Carlo Depletion Simulations
Bojan Petrovic (Georgia Tech), Jonathon Faulkner (Georgia Tech)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 180-190
Comparison of TMI-1 PWR SFCOMPO-2.0 Burnup Measurements with MCNP+BSOLVE Using Direct Multi-Group Cross Sections
Taylor S. Kimball (Univ. Utah), Glenn E. Sjoden (Univ. Utah)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 191-200
A Part Transfer Method for Burnup Credit in the MONK® Monte Carlo Code
Simon D. Richards (Amentum), Jessica A. Fildes (Amentum), David Hanlon (Amentum), Brian J. Jones (Amentum)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 201-210
Decay Heat Analysis of Non-LWR Spent Fuel Using SCALE
Yves Robert (ORNL), Germina Procop (ORNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 211-220
SMR Core Depletion and Spent Fuel Characterization with Nodal Code Ants
Topias Kähkönen (VTT Technical Research Centre of Finland)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 222-230
Verification of CASMO5 for Higher Enrichment and High Burnup Lattice Physics Analyses
Petri Forslund Guimarães (Studsvik Scandpower), Joshua Hykes (Studsvik Scandpower), Rodolfo Ferrer (Studsvik Scandpower)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 231-239
Research Reactor Core Loading Optimization: Enabling Machine Learning Applications by Employing Surrogate Models
Julia Bartos (Nuclear Research and Consultancy Group), Benjaminas Marcinkevicius (Nuclear Research and Consultancy Group), Bernard Erasmus (Nuclear Research and Consultancy Group), Christian Fedon (Nuclear Research and Consultancy Group), Edo Frederix (Nuclear Research and Consultancy Group)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 240-249
Bayesian Optimization for PWR-Core Loading Pattern Optimization
Zhou Yuancheng (Xi’an Jiaotong Univ.), Li Yunzhao (Xi’an Jiaotong Univ.), Wu Hongchun (Xi’an Jiaotong Univ.), Wei Shen (Conexus Nuclear Inc.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 250-259
High-fidelity Pebble Bed Reactor Depletion Based on Pebble Tracking Transport in Griffin
Yaqi Wang (INL), Joshua Hanophy (INL), Javier Ortensi (INL), Namjae Choi (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 262-271
Numerical Method Improvements in Griffin for Pebble Bed Reactors with a Focus on the Computation of Burnup
Joshua Hanophy (INL), Paolo Balestra (INL), Rodrigo de Oliveira (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 272-278
Accounting for Self-Shielding Effects in Advanced Inventory Simulation, Using Probability Table, Universal Curve Methods
Jean-Christophe Sublet (U.K. Atomic Energy Authority), Mark Gilbert (U.K. Atomic Energy Authority)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 279-287
Fast Burnup Calculation Method Based on Neutron Spectrum Reconstruction with Proper Orthogonal Decomposition and Regression Model
Tomoaki Watanabe (JAEA), Naoto Aizawa (Tohoku Univ.), Go Chiba (Hokkaido Univ.), Kenichi Tada (JAEA), Akio Yamamoto (Nagoya Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 288-297
An Efficient Variance-Based Uncertainty Decomposition Methodology for Nuclear Data in LWR Depletion Calculations
Lars Engelen (SCK CEN), Luca Fiorito (SCK CEN), Gert Van den Eynde (SCK CEN)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 302-311
Application of CASMO5 Nuclear Data Uncertainty Quantification to Similarity Analysis Using Integral Indices
Rodolfo Ferrer (Studsvik Scandpower), Joshua Hykes (Studsvik Scandpower)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 312-322
Depletion Perturbation Theory Methodology for Analyzing the Sensitivity of Advanced Activation Chains
Benjamin Murphy (Univ. New Mexico), Christopher Perfetti (Univ. New Mexico)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 323-332
Preliminary Sensitivity Analysis of Time-Dependent Code Outputs in Fuel Performance Models Using OFFBEAT for Future Calibration
Sara Maccario (Paul Scherrer Institute), Gustav Robertson (Uppsala Univ.), Edoardo Luciano Brunetto (École Polytechnique Fédérale de Lausanne), Alessandro Scolaro (Ecole Polytechnique Federale de Lausanne), Mathieu Hursin (Ecole Polytechnique Federale de Lausanne), Michel Saliba (École Polytechnique Fédérale de Lausanne)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 333-342
Recent Extensions of the Whole-Core Modelling Features in the WIMS® Reactor Physics Code
Glynn Hosking (Amentum), Kajetan Streciwilk (Amentum), Kornelia Wolodzko (Amentum), Brendan Tollit (Amentum)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 346-355
SIGAR: An APOLLO3® -Based Framework for PWR Analysis
Nicolas Gérard Castaing (CEA), Eve L. Ménédeu (CEA), Blaise Mathon (CEA), Amélie Rouchon (CEA), Neïl Zaim (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 356-365
Scarabée : A Free and Open-Source Lattice Physics Code
Hunter Belanger (Rensselaer Polytechnic Institute), Parth Singh (Rensselaer Polytechnic Institute)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 366-375
Global Symmetry Relations for Efficient COMET Core Calculations
Dingkang Zhang (Georgia Tech), Farzad Rahnema (Georgia Tech)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 376-385
Stabilizing the Consistent Quasidiffusion Method with Linear Prolongation
Dean Wang (Ohio State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 388-397
A Diffusion Synthetic Acceleration Scheme for THOR's AHOT-C0 Method on Unstructured Tetrahedral Meshes
Gokhan Pediz (NCSU), Yousry Azmy (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 398-407
Particle Transport Acceleration with 'Consistent' Eddington Factors
Tomas M. Paganin (Ohio State), Richard Vasques (Ohio State), Edward W. Larsen (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 408-418
Revisiting Stabilization Methods for 2D/1D Calculations in MPACT
Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 419-428
A Hybrid SN-Diffusion Method for Molten Salt Reactor Control Rod Modeling
Sun Myung Park (Univ. Illinois, Urbana-Champaign), Kathryn D. Huff (Univ. Illinois, Urbana-Champaign), Madicken Munk (Univ. Illinois, Urbana-Champaign)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 430-439
Response Matrix Equivalence Method Based on Relaxed Flux Continuity Equation and its Application to Reflector Homogenization for Diffusion Calculations
Sami Machach (Polytechnique Montréal), Alain Hebert (Polytechnique Montreal)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 440-449
High-Accuracy Critical Radii Analytic Expressions for Spherical Reflected Systems Based on Discontinuous Asymptotic Diffusion Theory
Shay I. Heizler (Hebrew Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 450-459
Adaptive Mesh Refinement of the Domain Decomposition+𝐿2-Jumps Method Applied to the Neutron Diffusion Equation on 3D Structured Meshes
Mario Gervais (CEA), François Madiot (CEA), Minh-Hieu Do (CEA), Patrick Ciarlet (ENSTA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 460-469
Correction Method of Few-Group Cross Sections for Core Analysis of High-Temperature Gas-Cooled Reactors
Amane Haga (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Go Chiba (Hokkaido Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 472-481
Towards Control Drums Homogenization in Microreactors: A Study on Neutron Absorption
Hadi Abuzlf (Ben-Gurion Univ. Negev), Erez Gilad (Ben-Gurion Univ. Negev)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 482-490
Extension of TRISO Double Heterogeneity Treatment in Griffin to Spherical Shell Geometry for Fluoride Salt-Cooled Pebble Bed Reactor
Hansol Park (ANL), Changho Lee (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 491-502
Hybrid Stochastic Deterministic Multigroup Cross Section Generation Method
Farzad Rahnema (Georgia Tech), Dingkang Zhang (Georgia Tech)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 503-511
DeCART2D Calculations of APR-1400 Benchmark Using Improved Cross Section Library Generation System
Chiheon Kim (Kyung Hee Univ.), Ho Jin Park (Kyung Hee Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 514-523
Preliminary Investigation of Dancoff Factor Treatment in Application of Direct Coupling Code System Using FRENDY Version 2 and GENESIS on Three-Dimensional LWR Fuel Assembly Problem
Tatsuya Fujita (Hokkaido Univ.), Go Chiba (Hokkaido Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 524-533
A Study of Goldstein-Cohen Parameter for a Subgroup Method Based on Intermediate Resonance Model in APOLLO3®
Terry Levy (CEA), Li Mao (CEA), Richard Sanchez (CEA), Emeline Rosier (CEA), Igor Zmijarevic (CEA), Frank Gunsing (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 534-543
A Simple Resonance Calculation Method for Flexible Geometry Using Equivalence Relation and Point-wise Cross Sections (ERPX)
A. Yamamoto (Nagoya Univ.), T. Endo (Nagoya Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 544-553
A Deterministic Dynamical Low-Rank Approach for Charged Particle Transport
Pia Stammer (Delft Univ. Technology), Tiberiu Burlacu (Delft Univ. Technology), Niklas Wahl (DKFZ), Danny Lathouwers (Delft Univ. Technology), Jonas Kusch (Norwegian Univ. of Life Sciences)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 556-565
Deterministic Transport of Coupled Energetic Light-Ions and Neutrons with Application to Inertial Confinement Fusion
Kyle S. Beling (LANL), James S. Warsa (LANL), Anil K. Prinja (Univ. New Mexico)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 566-575
Subgroup and Resonance Spectrum Expansion Self-Shielding Methods Using a Discontinuous Isogeometric Analysis Discrete Ordinate Discretisation of the Neutron Transport Equation
Kypros Donegan (Imperial College London), Luis J.W. Fernandes (Imperial College London), Alain Hébert (Ecole Polytechnique Montreal), Matthew D. Eaton (Imperial College London), Charles Latimer (Rolls-Royce), Seth G. Wilson (Rolls-Royce), József Kópházi (Budapest Univ. Technology and Economics)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 578-587
A Posteriori Source-Driven Spatial Error Estimators for Adaptive Mesh Refinement in the Context of SN-MOC Transport in a 1-D Slab Geometry
Alexis Anne (Commissariat a l'Energie Atomique), Emiliano Masiello (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 588-597
Offline Maximizing Minimally Invasive Proper Orthogonal Decomposition for Reduced Order Modeling of Sn Radiation Transport
Quincy Huhn (TAMU), Jean Ragusa (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 598-607
Machine-Learning-Based Pebble Power Reconstruction for Pebble-bed Reactor Analysis
Seongjin Jeong (ANL), Changho Lee (ANL), Shikhar Kumar (ANL), Hansol Park (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 608-616
Heuristic-Based Adaptive Mesh Refinement Applied to Ray Effect Mitigation Methods
Kevin C. Sawatzky (Univ. Illinois, Urbana-Champaign), April J. Novak (Univ. Illinois, Urbana-Champaign)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 618-627
Robust Positive and Monotone Schemes on Nonorthogonal Quadratures for Highly Anisotropic Scattering
Charles Bienvenue (Polytechnique Montréal), Ahmed Naceur (Polytechnique Montréal), Jean-François Carrier (Université de Montréal), Alain Hébert (Polytechnique Montréal)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 628-634
Assessing AI-Enhanced Single-Sweep Approximations for Transport Problems with Forward-Peaked Scattering in Slab Geometry
Japan K. Patel (Ohio State), Matthew C. Schmidt (Washington Univ. St. Louis), Anthony Magliari (Varian Medical Systems), Todd A. Wareing (Varian Medical Systems)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 635-643
Sweep-Based Uncollided-Flux Treatment On Unstructured Grids
Connor Woodsford (TAMU), Jean C. Ragusa (TAMU), Jim E. Morel (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 644-653
Continuous-Energy Deterministic Neutron-Transport Calculation Method Featuring Full Energy-domain Coupling and Function Expansion
Haopo Liu (Xi’an Jiaotong Univ.), Yunzhao Li (Xi’an Jiaotong Univ.), Xiaoyu Wen (Xi’an Jiaotong Univ.), Hongchun Wu (Xi’an Jiaotong Univ.), Liangzhi Cao (Xi’an Jiaotong Univ.), Wei Shen (Conexus Nuclear Inc.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 656-665
OpenSn: A Massively Parallel, Open-Source Simulation Environment for Discrete-Ordinate Radiation Transport
David Andrs (Sawtooth Simulations LLC), Pablo Garcia (TAMU), Zach Hardy (LANL), Daryl Hawkins (TAMU), Jim Morel (TAMU), Jean Ragusa (TAMU), Jason Rodriguez (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 666-675
Survey and Initial Results of Quantum Algorithms for Solving Neutronics Equations
Lincoln A. Johnston (Univ. Michigan), Jeanie Y. Qi (Univ. Michigan), Brian C. Kiedrowski (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 676-685
QUANTRA: An Efficient Tool for Neutron Transport Calculations Using Quantum-Inspired and Traditional Approaches
Mohamed Lahdour (Khalifa Univ.), Khurrum Saleem Chaudri (Khalifa Univ.), Mohammad Alrwashdeh (Khalifa Univ.), Saeed A. Alameri (Khalifa Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 686-695
GPU Accelerated SN Transport Calculation with Unstructured Meshes in STRAUM
Ao Zhang (Hanyang Univ.), Seungil Jeong (Hanyang Univ.), Ser Gi Hong (Hanyang Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 700-708
Performance Improvements of the Implicit Monte Carlo Method with Event-Based Vectorization on CPUs
Joseph Farmer (Univ. Notre Dame), Alex Long (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 709-717
Parallelization of Correlated Sampling Uncertainty Estimation in the iDTMC (Improved Deterministic Truncation of Monte Carlo) Analysis of Sodium-Cooled Fast Reactors
Sunjoo Yoon (KAIST), Inyup Kim (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 718-727
Introduction of GPU-Enabled CMFD Acceleration for Performance Enhancement of Neutron Transport Code STREAM3D-GPU
Fathurrahman Setiawan (Ulsan Nat'l Institute Science and Technology), Siarhei Dzianisau (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 728-737
Deep Operator Network Based Surrogate Model for Neutron Transport Computation
Md Hossain Sahadath (Rensselaer Polytechnic Institute), Qiyun Cheng (Rensselaer Polytechnic Institute), Shaowu Pan (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 742-751
A CNN-Based Physics-Informed Neural Networks for Solving the Neutron Diffusion Equation
Jaeguk Lee (Seoul Nat'l Univ.), Hyung Jin Shim (Seoul Nat'l Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 752-761
Use of Bayesian Polynomial Regression Methods to Model Uncertainty in Few-Group Cross-Section Libraries
Yi Meng Chan (Royal Institute of Technology), Jan Dufek (Royal Institute of Technology)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 762-771
Machine Learning Algorithms for Neutron and Gamma Radiation Discrimination
Abigail Artman (U.S. Naval Academy), Jennie Hill (U.S. Naval Academy), Joseph Latta (U.S. Naval Academy), Hatem ElBidweihy (U.S. Naval Academy)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 772-781
Development of Variational Neural Networks for Uncertainty Quantification of Nuclear Applications
Logan A. Burnett (Univ. Michigan), Umme Mahbuba Nabila (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 784-793
Towards Explainable AI in Nuclear: Introducing Ad Hoc Model Explainability
Alex Xu (Univ. Michigan), Nataly Panczyk (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 794-803
Interpretable Machine Learning Regression for Nuclear Applications with Kolmogorov-Arnold Networks (KAN)
Omer Erdem (Univ. Michigan), Nataly Panczyk (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 804-813
High-Resolution Predictions of the Fuel and Cladding Temperatures for the 3D PWR Core with Artificial Neural Networks Trained on CTF
Marianna Papadionysiou (École Polytechnique Fédérale de Lausanne), Gregory Delipei (NCSU), Maria Avramova (NCSU), Hakim Ferroukhi (Paul Scherrer Institute), Kostadin Ivanov (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 814-823
On the Recoverability of Reactor Dynamics from Point Kinetics Data Using SINDYc
Dean Price (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 826-834
A Multiphysics Reduced Order Model in TRIGA Reactors Using Dynamic Mode Decomposition
John Ross (Univ. Texas, Austin), Ben Collins (Univ. Texas, Austin), Cole Gentry (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 835-844
Load-Following Control in Microreactors with Deep Reinforcement Learning
Leo Tunkle (Univ. Michigan), Kamal Abdulraheem (Univ. Michigan), Maxime Amans (Univ. Michigan), Majdi I. Radaideh (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 845-854
Meta-Modeling of the ALGO Code for Optimized Load-Follow Operations in Nuclear Reactor Clusters
Hamza Benabbes-Taarji (SUBATECH), Jean-Michel Do (CEA), Thibault Moulignier (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 855-864
Harmonic Analysis of a Repositioning Plan Optimization Problem
Martin Desombre (Univ. Littoral Cote d'Opale), Baptiste Magnaudet (CEA), Jean-Michel Do (CEA), Jean Fromentin (Univ. Littoral Cote d'Opale), Sébastien Verel (Univ. Littoral Cote d'Opale)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 866-875
Sequential Optimal Experimental Design for Efficient Learning of Reduced Order Models with Application to Microreactor Pin Powers
Brendan Kochunas (Univ. Michigan), Nazmul Hossain (Univ. Michigan), Dean Price (Univ. Michigan)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 876-885
Physics-Informed ML using RAPID for Predicting Eigenvalue and 3-D Fission Distribution in JSI TRIGA Mark-II Research Reactor
Timothy Franck (Virginia Tech), Alireza Haghighat (Virginia Tech), Luka Snoj (Jožef Stefan Institute)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 886-895
Designing Energy Discretisations Using a Genetic Algorithm for Sensitivity Studies in Lead-Cooled Fast Reactors Using a Genetic Algorithm
Emilie Delvaux (Université libre de Bruxelles), Federico Grimaldi (Université libre de Bruxelles), Nicoló Abrate (Politecnico di Torino), Alex Aimetta (Politecnico di Torino), Mattia Massone (ENEA), Victor J. Casas-Molina (SCK CEN), Antonin Krása (SCK CEN), Pierre-Etienne Labeau (Université libre de Bruxelles)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 896-905
A Study of Temperature Feedback in the DARWIN Core Concept with Comparison of Monte Carlo and Deterministic Approaches
Anze Mihelcic (Jozef Stefan Institute), Dušan Čalič (Jozef Stefan Institute), Luka Snoj (Jozef Stefan Institute)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 912-921
On-the-fly Temperature Treatment Routine for Unresolved Resonance Probability Table Sampling in Serpent 2
Jaakko Leppänen (VTT Technical Research Centre of Finland)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 922-931
Convergence Analysis on Large Scale Models Simulated Using the GUARDYAN-SUBCHANFLOW Coupled Code System
Elod Pázmán (Budapest Univ. Technology and Economics), Gabor Tolnai (Budapest Univ. Technology and Economics), David Legrady (Budapest Univ. Technology and Economics), Tamas Hajas (Budapest Univ. Technology and Economics)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 932-941
Multi-Material Cell Treatments in the LLNL Imp IMC Code
Evan S. Gonzalez (LLNL), Patrick S. Brantley (LLNL), Matthew J. O'Brien (LLNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 942-951
A Hybrid Cross Section Generation Method Using Monte Carlo Codes for Nuclear Thermal Propulsion Nodal Diffusion Analysis
Jacob Smith (Georgia Tech), Dan Kotlyar (Georgia Tech)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 954-963
Clarification on the Various Methods of Calculating the P1 Transport Cross Section Using Monte Carlo Codes
Vidor H. Lujan (Georgia Tech), Bailey Painter (Georgia Tech), Dan Kotlyar (Georgia Tech)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 964-972
Multigroup Cross Section Generation with the Shift Monte Carlo Code
Tara Pandya (ORNL), Friederike Bostelmann (ORNL), Donny Hartanto (ORNL), Steven Hamilton (ORNL), Matthew Jessee (ORNL), Nicholas Luciano (ORNL), Tarek Ghaddar (ORNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 973-983
Implementation of the Iterated Fission Probability Method in OpenMC to Compute Adjoint-Weighted Kinetics Parameters
Joffrey Dorville (ANL), Luke Labrie-Cleary (Copenhagen Atomics), Paul K. Romano (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 984-994
Monte Carlo Sampling Strategy for a Non-Perturbative Approach to the Neutron Noise Equation: a Proof of Concept
Axel Fauvel (CEA), Amélie Rouchon (CEA), Davide Mancusi (CEA), Andrea Zoia (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 996-1005
Comparison of Branching and Branchless Zero-Variance Games
Thayz Gomes Ferreira (CEA), Francesco Rossi (CEA), Alexis Jinaphanh (CEA), Davide Mancusi (CEA), Andrea Zoia (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1006-1015
Real Variance Estimation in iDTMC Method Using Autoregressive (1) Model
Jaehyeong Jang (KAIST), Yonghee Kim (KAIST)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1016-1025
Selection-Driven Evolutionary Population Control for Kinetic Monte Carlo Variance Reduction
Martin Skretteberg (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1026-1035
Stochastic Method for Delayed Neutron Precursors Transport in Liquid Fuel
Mathis Caprais (CEA), Daniele Tomatis (NewCleo)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1038-1047
Impact of the Delayed Energy Deposition in TREAT on Transient Dynamics
Paul A. Ferney (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1048-1054
The Effect of Negative Sample Paths on the Accuracy of Numerical Solutions for Stochastic Point-Kinetics
Théophile Bonnet (Univ. Cambridge), Terence Tsui H. Lung (Warwick Univ.), Valeria Raffuzzi (Univ. Cambridge), Oliver Tough (Durham Univ.), Martin Skretteberg (Univ. Cambridge)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1055-1064
Simulated Pulsed Neutron Experiments of the Inherently Safe Subcritical Assembly
Alessandro P. Ingegno (Univ. California, Berkeley), William Zywiec (LLNL), Daniel Siefman (Univ. California, Berkeley)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1065-1074
Peacock: A Monte Carlo Code with Shared Memory Paralellism for Consumer-Grade Computing Architectures
William C. Dawn (Studsvik Scandpower)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1076-1083
A Practical Guide to Parsing MCNP Inputs: Lessons Learned from Implementing Context-Free Parsing in MontePy
Micah D. Gale (INL), Travis J. Labossiere-Hickman (INL), Brenna A. Carbno (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1084-1093
Development of an Event Tracking Feature in OpenMC for Neutron Spectroscopy and Scatter Camera Systems
Michel Saliba (École Polytechnique Fédérale de Lausanne), Paul Romano (ANL), John Tramm (ANL), Erik B. Knudsen (United Neux), Daniel Siefman (Univ. California, Berkeley), Andreas Pautz (Paul Scherrer Institute), Oskari Pakari (École Polytechnique Fédérale de Lausanne)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1094-1103
Radiation Shielding Analysis of LEA in APS using FLUKA, PHITS and MARS Monte Carlo Radiation Transport Codes
Sunil Chitra (ANL), Jeffrey Dooling (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1104-1113
Polygonal Functional Expansion Tallies Using Transformed Zernike Polynomials
Joseph F. Specht IV (Univ. Illinois, Urbana-Champaign), April J. Novak (Univ. Illinois, Urbana-Champaign)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1116-1125
Using Moment-Based Functional-Expansion Tallies to Construct the Linear Discontinuous Finite-Element Flux in Tetrahedral-Mesh Monte Carlo Simulations
Pablo A. Vaquer (LANL), Michael E. Rising (LANL), Joel A. Kulesza (LANL), Colin A. Weaver (LANL), Simon R. Bolding (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1126-1136
Working with Bézier Curves as Nonorthogonal Bases for Functional Expansion Tallies
Micah D. Gale (INL), Patrick Shriwise (ANL), Paul Wilson (Univ. Wisconsin, Madison)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1137-1146
Does Inherent Randomness in Monte Carlo Transport Calculations Mitigate the Effect of Poor Random Number Generators?
Gibson D. Prall (Y-12 National Security), Christopher M. Perfetti (Univ. New Mexico)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1147-1153
Small Sample Reactivity Worth Calculation: Comparison of Serpent2 and TRIPOLI4 Perturbation Techniques
Federico Di Croce (SCK CEN), Pierre Leconte (CEA), Federico Grimaldi (SCK CEN), Antonin Krása (SCK CEN), Pierre-Etienne Labeau (Université Libre de Bruxelles), Jan Wagemans (SCK CEN)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1156-1165
Revisiting the Reactor Period Capabilities in TRIPOLI-4®
Cecilia Montecchio (CEA), Davide Mancusi (CEA), Vincent Lamirand (École Polytechnique Fédérale de Lausanne), Wilfried Monange (IRSN), Andrea Zoia (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1166-1175
Multi Cycle Core Follow Calculations for Hanbit Unit 3 Using the McCARD/MASTER Code System with ENDF/B-VII.1 and ENDF/B-VIII.0 Evaluated Nuclear Data Libraries
Jeong Woo Park (Kyung Hee Univ.), Ho Jin Park (Kyung Hee Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1176-1185
Fourier Analysis of Fission Matrix Convergence Acceleration
Paul Cosgrove (Univ. Cambridge), Zi Liang Tan (SNRSI)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1188-1197
A Monte Carlo Implementation of the 𝜁-Eigenvalue Equation
Valeria Raffuzzi (Univ. Cambridge), Nicolo' Abrate (Politecnico di Torino), Sandra Dulla (Politecnico di Torino)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1198-1207
A Residual Monte Carlo Algorithm for Continuous Energy Neutron Transport with Elastic Scattering and Fission
Massimo Larsen (Oregon State), Simon Bolding (LANL), Todd Palmer (Oregon State), Jim Morel (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1208-1217
A Thick-Target Bremsstrahlung Model with Angularly-Dependent Emission in the MCNP6 Code
Aaron G. Tumulak (LANL), Simon R. Bolding (LANL), Jesse F. Giron (LANL), Anthony Zukaitis (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1218-1227
Time-Dependent Power Reconstruction Methodology Using Interpolated Fractions and Peaking Factors in the Mixcoatl 2.0 Software
Vincent Laboure (BWX Technologies), Chase Lawing (BWX Technologies), Phil Hegedus (BWX Technologies), Bryan Zilka (BWX Technologies)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1232-1240
Solving Point Kinetics Equations Using Matrix Exponentials and Reactivity Extrapolation
Emmanuel Lefevre (TechnicAtome), Mael Akouz (TechnicAtome)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1241-1250
Application of the Pathline Method to the Aircraft Reactor Experiment
Mathis Caprais (CEA), Nathan Greiner (CEA), André Bergeron (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1251-1260
The Parareal Algorithm as Applied to Coupled Point Kinetics and Thermal-Hydraulics Models for Reactor Transients
Timothy M. Kiefer (NCSU), Nick J. Adamowicz (Bettis Atomic Power Lab), Gabriel Kooreman (Bettis Atomic Power Lab)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1261-1270
Coupling of Serpent, SUBCHANFLOW and SuperFINIX for Transient Simulations
Riku Tuominen (VTT Technical Research Centre of Finland), Ville Valtavirta (VTT Technical Research Centre of Finland)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1272-1280
Coupled Neutronics and Thermal Hydraulics Simulations of a BWR Fuel Channel in the Version5 Environment
Raphael Guasch (Polytechnique Montréal), Clément Huet (Polytechnique Montréal), Alain Hébert (Polytechnique Montréal), Cédric Béguin (Polytechnique Montréal), Guy Marleau (Polytechnique Montréal)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1281-1290
Application of Expanded Transfer Functions for Predicting Two-Group Macroscopic Cross Sections in a 3D Nuclear Thermal Propulsion Core
Bailey Painter (Georgia Tech), Dan Kotlyar (Georgia Tech)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1291-1300
Serpent - BISON - THM Preliminary Multiphysics Modeling of a Nuclear Thermal Propulsion System Fuel Assembly
Isaac Naupa (INL), Stefano Terlizzi (Penn State), Mark DeHart (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1301-1310
Verification of a Multiphysics Gas-Cooled Reactor Simulation via the Method of Manufactured Solutions
Zane G. Tucker (Oregon State), Todd S. Palmer (Oregon State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1312-1321
Pebbles' Life Cycle Analysis in Salt-Cooled Pebble Bed Reactor for Enhanced Fuel Performance Assessment
Ludovic Jantzen (Univ. California, Berkeley), Yves Robert (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1322-1331
In-Memory, Fully-Parallel Coupling of GeN-Foam and OFFBEAT: Towards a New Milestone in High-Fidelity, Finite-Volume Nuclear Reactor Simulation
Giovanni Nervi (École Polytechnique Fédérale de Lausanne), Alessandro Scolaro (Ecole Polytechnique Federale de Lausanne), Thomas Guilbaud (Ecole Polytechnique Federale de Lausanne), Carlo Fiorina (TAMU), Mathieu Hursin (Ecole Polytechnique Federale de Lausanne)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1332-1341
Cell-Wise Temperature and Deformation Reactivity Feedback Modeling in Heat Pipe-Cooled Microreactors
Chiara Genoni (TAMU), Carlo Fiorina (TAMU), Vefa Kucukboyaci (Westinghouse Electric Co.), Fausto Franceschini (Westinghouse Mangiarotti), Alessandro Scolaro (École Polytechnique Fédérale de Lausanne)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1342-1351
Modelling of a Neutron Source Test Bed for the Fusion Fuel Cycle
Mark R. Gilbert (U.K. Atomic Energy Authority), David Foster (U.K. Atomic Energy Authority), Steven C. Bradnam (U.K. Atomic Energy Authority), Andrew Davis (U.K. Atomic Energy Authority), Vladimir Martis (U.K. Atomic Energy Authority), Mikhail Yu. Lavrentiev (U.K. Atomic Energy Authority)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1354-1363
Method of Eigenfunction Expansion Applied to Laplace's Equation in Problems Consisting of Multilayer Concentric Spheres
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1364-1373
Monte Carlo Multiphysics on Moving Meshes: Initial Verification and Case Studies
Mahmoud Eltawila (Univ. Illinois, Urbana-Champaign), April J. Novak (Univ. Illinois, Urbana-Champaign), Pierre-Clement A. Simon (INL), Guillaume Giudicelli (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1374-1383
MOOSE Web Server Interface: A Message-Based External Interface for Multiphysics Simulations
Logan Harbour (INL), Patrick Shriwise (ANL), April Novak (Univ. Illinois, Urbana-Champaign), Derek Gaston (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1384-1393
Machine Learning Applied to the Prediction of (n, 2n) Cross Sections
L. Morgan (AWE), A. Stott (AWE), S. Sullivan (University of Surrey)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1398-1407
The Influence of Parent Feeding on Delayed-Neutron Group Parameter Estimation from Weighted Nonlinear Least-Squares Regressions
Yanuar Ady Setiawan (Ulsan Nat'l Institute Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute Science and Technology)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1408-1417
Predicting (n,p) and (n,𝛼) Cross Sections Using Decision Trees
Rohan Gaya (Univ. Cambridge), Valeria Raffuzzi (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge), Lee Morgan (AWE)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1418-1426
Development of a Representative Molten Chloride Fast Reactor Model to Assess the Impact of Nuclear Data
Rakim Hirji (Georgia Tech), Germina Procop (ORNL), Friederike Bostelmann (ORNL), Rabab Elzohery (ORNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1427-1436
Numerical Solutions of the Inventory Equation and Graph Theory
David Foster (U.K. Atomic Energy Authority)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1438-1444
Linearized Thermal Incoherent Inelastic Neutron Scattering Sampling Distributions in the Direct 𝑆(𝛼, 𝛽) Method
Camden E. Blake (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1445-1454
Implementation of Windowed Multipole Cross Section Capability into MCNP6.3
Matthew Lazaric (Univ. New Mexico), Christopher Perfetti (Univ. New Mexico), Michael E. Rising (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1455-1463
AAA for Multipole Cross-Section Fitting
Gavin Ridley (Aalo Atomics), Benoit Forget (MIT)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1464-1473
Accurate Reduced Floating-Point Precision Implicit Monte Carlo
Simon Butson (Oregon State), Mathew Cleveland (LANL), Alex Long (LANL), Todd Palmer (Oregon State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1478-1487
Reduced Memory Discretization Scheme for Time-Dependent Thermal Radiative Transfer Problems
Rylan C. Paye (NCSU), Joseph M. Coale (LANL), James S. Warsa (LANL), Dmitriy Y. Anistratov (NCSU), Connor A. Woodsford (LANL), Jim E. Morel (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1488-1495
Implicit Opacities in Thermal Radiative Transfer
Samuel Olivier (LANL), Quincy A. Huhn (TAMU), James S. Warsa (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1496-1505
Deterministic Particle Transport for Reducing Noise in Thermal Radiative Transfer
Benjamin L. Estrada (Oregon State), Todd S. Palmer (Oregon State), Nicholas A. Gentile (LLNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1506-1515
A Hybrid Second Moment Method for Thermal Radiative Transfer
Michael Pozulp (LLNL), Terry Haut (LLNL), Patrick Brantley (LLNL), Samuel Olivier (LANL), Jasmina Vujic (Univ. California, Berkeley)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1518-1527
A Second Moment Transport Method for Semi-Implicit Nonlinear Thermal Radiative Transfer
Joseph M. Coale (LANL), James S. Warsa (LANL), Samuel Olivier (LANL), Dmitriy Y. Anistratov (NCSU), Jim E. Morel (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1528-1537
Generalized Non-Equilibrium Marshak Wave Solutions in the Gray Diffusion Approximation
Menahem Krief (Racah Institute), Ryan G. McClarren (Univ. Notre Dame)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1538-1546
Multilevel Method with Low-Order Equations of Mixed Types and Two Grids in Photon Energy for Thermal Radiative Transfer
Dmitriy Y. Anistratov (NCSU), Terry S. Haut (LLNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1547-1556
Fully Coupled Adjoint-Based Perturbation Theory for dynAmIcs and heat traNsfer (CAPTAIN) Multiphysics for Nuclear Transients
Alexis Maldonado (Univ. New Mexico), Christopher M. Perfetti (Univ. New Mexico)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1560-1569
Uncertainty Quantification of Bifurcations in the Rayleigh-Benard Problem for Molten Salts
Fadel M. Nasr (NCSU), Yousry Azmy (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1570-1579
Uncertainty Quantification of Transients with Derived Kinetic Data
Maximiliano Velasco (NCSU), Scott Palmtag (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1580-1589
Application of Fuel Depletion Chain Simplification to Experiment Analysis in the Advanced Test Reactor
Travis J. Labossiere-Hickman (INL), Olin W. Calvin (INL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1592-1601
Uncertainty Quantification for Watts Bar 1 PWR Using High-Fidelity Whole Core Model in WIMS® and the Latin Hypercube Sampling Method
Jean Lavarenne (Amentum), Tim Ware (Amentum), Magda Stefanowska-Skrodzka (Amentum), Kornelia Wolodzko (Amentum), William Poole (Amentum), Peter Smith (Amentum), Glynn Hosking (Amentum), Brendan Tollit (Amentum)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1602-1611
Uncertainty Quantification Of Fuel Assembly Bow In Pressurized Water Reactor Through a Thermomechanical Simulation
Ali Abboud (CEA), Josselin Garnier (École Polytechnique Fédérale de Lausanne), Bertrand Leturcq (CEA), Julien Pacull (Framatome), Olivier Fandeur (CEA), Stanislas de Lambert (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1612-1621
Analytic Sensitivity Coefficients for Bethe's Solution of the Neutron Slowing Down Equation
Colin A. Weaver (LANL), Michael E. Rising (LANL), Joel A. Kulesza (LANL), Pablo A. Vaquer (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1622-1634
Nuclear Data Impact on HTR-10 Pebble Bed Reactor Metrics
Rabab Elzohery (ORNL), Friederike Bostelmann (ORNL), Germina Procop (ORNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1636-1645
Identifying Nuclear Data Uncertainties to the Integral keff in the MCFR-D Reactor
Bobbi Harper (TerraPower), Tommy Cisneros (TerraPower)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1646-1655
Cross Section Discrepancies in Neutron-Carbon Interactions at 14 MeV: A Sensitivity and Uncertainty Analysis
Enrica Belfiore (CEA), Mehdi Ben Mosbah (CEA), Rodolphe Antoni (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1656-1664
Eigenvalue Sensitivity to Problem Geometry by Coordinate Perturbation for Diffusion Equation
Mikolaj Adam Kowalski (CEA), Anuj Dubey (Univ. Cambridge), Eugene Shwageraus (Univ. Cambridge)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1666-1675
Preliminary Results on Bayesian Inverse UQ for OECD/NEA WPNCS Subgroup 14 Benchmark Exercise for Error Recovery and Experimental Coverage
Christopher Brady (NCSU), Sofiia Asadchykh (NCSU), Ziyu Xie (NCSU), Xu Wu (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1676-1685
Exploring A Two-Level, Control-Variate Monte Carlo Method for Uncertainty Quantification in Criticality Safety
Rabab Elzohery (ORNL), Jeremy Roberts (Kansas State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1686-1695
Advancing Uncertainty Reduction -- Applications for ACCRUE Relevance Index in Nuclear Criticality Safety
Jeongwon Seo (Univ. Texas, Austin), Ugur Mertyurek (ORNL), Kevin T. Clarno (Univ. Texas, Austin)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1696-1705
A Low-Fidelity Covariance Library in EPICS for Photon-Electron Radiation Transport Applications
Mekiel Olguin (Sandia), Christopher M. Perfetti (Univ. New Mexico), Aaron J. Olson (Sandia), Brian C. Franke (Sandia)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1708-1716
Preliminary Verification of Fixed-Source Sensitivity and Uncertainty Analysis in OpenMC
Bamidele Ebiwonjumi (MIT), Benoit Forget (MIT), Ethan Peterson (MIT)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1717-1725
CWENO Interpolation for Non-Oscillatory Stochastic Collocation in Uncertainty Quantification Problems
Alina Chertock (NCSU), Arsen S. Iskhakov (Kansas State), Anna Iskhakova (Kansas State), Alexander Kurganov (Southern Univ., China)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1726-1735
Advancing the STS Neutron Moderator Optimization with an Automated Workflow and Unstructured Mesh Modeling
Kristel Ghoos (ORNL), Lukas Zavorka (ORNL), Igor Remec (ORNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1736-1745
On the Applicability of Generalized Perturbation Theory for Enforcing Numerical Accuracy Enhancements in Embedded Search Procedures
Rene van Geemert (Framatome)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1750-1760
Adjoint Sensitivity Analysis of a 1D Stationary Neutronics-Thermohydraulics Coupled Molten Salt Reactor Model
Ruggero Rosselli (CEA), Grégoire Allaire (École Polytechnique), Cyril Patricot (CEA), Maria Adela Puscas (CEA), François Madiot (CEA), Nathan Greiner (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1761-1770
Efficient Neutron Detector Response Modeling for Non-Stationary Volumetric Sources Using Adjoint Methods
Jason Rodriguez (TAMU), Jean C. Ragusa (TAMU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1771-1780
Implementation of the Multigroup Neutron Diffusion Equation Using Tensor Formulations in PyTorch
Kajetan Streciwilk (Amentum), Brendan Tollit (Amentum), Paul Smith (Amentum), Simon Cox (Amentum), Boyang Chen (Imperial College London), Christopher C. Pain (Imperial College London)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1782-1791
Progress Porting LLNL Monte Carlo Transport Codes to the AMD Instict MI300A APU
Shawn A. Dawson (LLNL), Ryan C. Bleile (LLNL), Patrick S. Brantley (LLNL), Evan S. Gonzalez (LLNL), M. Scott McKinley (LLNL), Matthew J. O'Brien (LLNL), Mike M. Pozulp (LLNL), Alex P. Robinson (LLNL), Max Yang (LLNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1792-1801
Implementation and Performance Analysis of the Transient Solver in STREAM3D-GPU
Saisundar Mohanty (Ulsan Nat'l Institute Science and Technology), Siarhei Dzianisau (Ulsan Nat'l Institute Science and Technology), Murat Serder Aygul (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1802-1810
Performance Evaluation of GREAPMC for Continuous Energy Reactor Physics Problems
Muhammad Rizwan Ali (Ulsan Nat'l Institute Science and Technology), Murat Serdar Aygul (Ulsan Nat'l Institute Science and Technology), Deokjung Lee (Ulsan Nat'l Institute Science and Technology)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1811-1820
Linear Source Random Ray on GPU
Rufus Neame (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge), John Tramm (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1822-1831
Correcting k-eff-Normalisation-Induced Bias in the Time-Dependent Random Ray Method
Maximilian Kraus (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge), John Tramm (ANL), Eugene Shwageraus (Univ. Cambridge)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1832-1841
Coupled 1D Neutronics and Thermal-Hydraulics Modelling with the Random Ray Method
Lucy Bland (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1842-1850
Randomized Quasi-Monte Carlo Sampling in the Random Ray Method for Neutron Transport Simulations
Samuel Pasmann (Thea Energy), John Tramm (ANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1851-1858
Hybrid Weight Window Techniques for Time-Dependent Monte Carlo Neutronics
Caleb Shaw (NCSU), Dmitriy Anistratov (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1861-1870
Convergence of Multi-Level Hybrid Monte Carlo Methods for 1-D Particle Transport Problems
Vincent N. Novellino (NCSU), Dmitriy Y. Anistratov (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1871-1880
Post-Processing Results From a Monte Carlo Neutron Transport Code Using Compressed Sensing
Ethan Lame (Oregon State), Camille Palmer (Oregon State), Todd Palmer (Oregon State), Ilham Variansyah (Oregon State), Ryan McClarren (Univ. Notre Dame)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1881-1890
A Batch Power Iteration Approach for the Iterative Quasi-Monte Carlo Method Using a Randomized-Halton Sequence
Samuel Pasmann (Thea Energy), Ilham Variansyah (Oregon State), C.T. Kelley (NCSU), Ryan G. McClarren (Univ. Notre Dame)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1892-1900
Monte Carlo Uncertainty Quantification and Sensitivity Analysis for the C5G7 Benchmark
Kayla B. Clements (Oregon State), Todd S. Palmer (Oregon State), Aaron J. Olson (Sandia), Gianluca Geraci (Sandia), Ilham Variansyah (Oregon State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1901-1910
Derivative Source Method for Monte Carlo Transport Calculation of Sensitivities to Material Densities and Dimensions
Ilham Variansyah (Oregon State), Ryan G. McClarren (Univ. Notre Dame), Todd S. Palmer (Oregon State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1911-1921
Implicit Collision Multiplicity Adjustment for Efficient Monte Carlo Transport Simulation of Reactivity Excursion
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1922-1931
Enabling GPU Portability into the Numba-JITed Monte Carlo Particle Transport Code MC/DC
Joanna Piper Morgan (Oregon State), Braxton Cuneo (Seattle Univ.), Ilham Variansyah (Oregon State), Kyle E. Niemyer (Oregon State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1934-1943
Comparing the Performance of MC/DC's on-GPU Event-Based Processing Methods in Multigroup and Continuous-Energy Problems
Braxton Cuneo (CEMeNT), Joanna Piper Morgan (CEMeNT), Ilham Variansyah (CEMeNT), Kyle E. Niemeyer (CEMeNT)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1944-1953
Improvements in MC/DC Domain Decomposition Functionality
Alexander Mote (Oregon State), Todd Palmer (Oregon State), Lizhong Chen (Oregon State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1954-1961
A Hierarchy of Parallel-Robust Stochastic Media Radiation Transport Models
Aaron Olson (Sandia), Luke Kersting (Sandia), Kerry Bossler (Sandia), Revolution Rivera-Felix (Sandia)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1966-1975
Advances in Stochastic Geometry Modelling in MONK and MCBEND, the Importance of Stochastic Models, and an Approach to Validation
Simon D. Richards (Amentum), Jessica A. Fildes (Amentum), Richard P. Hiles (Amentum), Brian J. Jones (Amentum), Paul N. Smith (Amentum)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1976-1985
Three-Point Correlations in Poisson Media
Alec Shelley (Stanford), Aaron Olson (Sandia), Gianluca Geraci (Sandia)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1986-1995
The Stochastic Point Reactor Equation with Thermal Feedback
Chen Dubi (Nuclear Research Center Negev), Anil K. Prinja (Univ. New Mexico)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 1996-2005
Estimating the Ensemble-Average Effective Multiplication Factor and Neutron Scalar Flux Profile in Statistically Homogeneous Random Media Using a Nonclassical Model
Leonardo Rodrigues da Costa Moraes (Universidade Estado Rio de Janeiro), Ricardo Carvalho de Barros (Universidade Estado Rio de Janeiro), Hermes Alves Filho (Universidade Estado Rio de Janeiro), Richard Vasques (Ohio State)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2008-2017
Random Media Criticality Analysis Using the Randomized Fourier Series for Arbitrary-Shaped Power Spectrum
Taro Ueki (JAEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2018-2027
Subcriticality Estimation Without Point Kinetics Parameters Based on Autocovariance of Reactor Noise Using Delayed Neutron Components
Tomohiro Endo (Nagoya Univ.), Ryoga Hirota (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Watanabe (Kyushu Univ.), Genichiro Wakabayashi (Kindai Univ.), Kengo Oda (Hokkaido Univ.), Junichi H. Kaneko (Hokkaido Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2028-2037
Reactivity Estimation in Dollar Units Based on Bayesian Monte Carlo Using Autocovariance of Reactor Noise Measurement
Ryoga Hirota (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Watanabe (Kyushu Univ.), Genichiro Wakabayash (Kindai Univ.), Kengo Oda (Hokkaido Univ.), Junichi H. Kaneko (Hokkaido Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2038-2047
Effects of Models Used in Stochastic Fission Event Energy Deposition Distribution Simulations
Patrick O'Rourke (LANL), Amy Lovell (LANL), Anil Prinja (Univ. New Mexico), Scott Ramsey (LANL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2050-2059
Implicit Monte Carlo Thermal Radiative Transfer for Three-Dimensional Binary Stochastic Media: Markovian and Renewal Material Statistics
Patrick S. Brantley (LLNL), Vincent N. Novellino (NCSU)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2060-2069
Monte Carlo Particle Transport in Renewal Statistical Media
Dominic A. Lioce (Univ. California, Berkeley), Patrick S. Brantley (LLNL), Anil K. Prinja (Univ. New Mexico)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2070-2080
A Generalized Master Equation for Transport in Binary Random Media with Renewal Statistics
Anil K. Prinja (Univ. New Mexico), Dominic A. Lioce (Univ. California, Berkeley)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2081-2090
Comparison of the ECCO/ERANOS and APOLLO3(r) Code for Molten Salt Fast Reactors Design Studies
Dusan Marjanovic (CEA), Nicolin Garnier (CEA), Giogio Valocchi (CEA), Jean Tommasi (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2094-2102
Modified Algorithm for Taking into Account Delayed Neutron Precursor Movement in the Improved Quasi-Static Scheme of the SIMMER-III Code
Barbara Kędzierska (Karlsruhe Institute of Technology), Andrei Rineiski (Karlsruhe Institute of Technology), Yoshiharu Tobita (Karlsruhe Institute of Technology)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2103-2112
Graphite-Moderated Molten Salt Reactor Progression Problems
Cole A. Gentry (Univ. Texas, Austin), Rok Krpan (TAMU), Kevin Clarno (Univ. Texas, Austin), Carlo Fiorina (TAMU), Jean Ragusa (TAMU), Benjamin Collins (Univ. Texas, Austin)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2113-2122
The Neutronics Codes FENNECS and FRENETIC: Code-to-code Benchmarking on Lead and Sodium-cooled Fast Reactors
Nicolo' Abrate (Politecnico di Torino), Jeremy Bousquet (GRS), Sandra Dulla (Politecnico di Torino), Silvia lo Muzio (GRS), Armin Seubert (GRS), Christian Vita (Politecnico di Torino)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2123-2132
Single Grid Error Estimate in Two-Dimensional Neutron Transport Problems
Ben Whewell (Univ. Notre Dame), Ryan G. McClarren (Univ. Notre Dame)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2134-2143
Verification Methods for the AGORA Geometry Navigation Engine of the TRIPOLI-5 Monte Carlo Code
Coline Larmier (CEA), Davide Mancusi (CEA), Vincenzo di Blasi (CEA), Andrea Zoia (CEA)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2144-2153
Ants Solution to IAEA-Hex Kinetics Benchmark
Antti Rintala (VTT Technical Research Centre of Finland)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2154-2162
Validation of OpenMC Using the KRUSTY Component Critical Experiments
Michael Anthony Mendes (Univ. Illinois, Urbana-Champaign), April J. Novak (Univ. Illinois, Urbana-Champaign)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2163-2172
EDIM Local Power History and Burnup Inference Based on Destructive Assay Data
Shiming Yin (Purdue Univ.), Tarikul Islam (Purdue Univ.), Ugur Mertyurek (ORNL), Germina Procop (ORNL), Hany Abdel-Khalik (Purdue Univ.)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2176-2185
Activation Calculation Comparison for FISPACT-II, ORIGEN, and OpenMC
Jin Whan Bae (ORNL), Yves Robert (ORNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2186-2195
Multi-Cycle Neutronics Verification in the Kraken Framework
Ville Valtavirta (VTT Technical Research Centre of Finland)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2196-2205
Alpha Eigenvalue and Beta-Effective Calculations of High Multiplication Uranium Experiments
William Zywiec (LLNL), Jesse Norris (LLNL), Samuel Varghese (LLNL), David Heinrichs (LLNL), Daniel Siefman (LLNL), Edward Lent (LLNL), Chuck Lee (LLNL), Anthony Nelson (LLNL)
Proceedings | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) | Denver, CO, April 27-30, 2025 | Pages 2206-2214
