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Home / Publications / Journals / Nuclear Science and Engineering / Volume 199 / Number 1S

Volume 199

Number 1S

Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using Modern Optimization Algorithms

Khaldoon Al-Dawood, Scott Palmtag

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S664-S679

Research Article / dx.doi.org/10.1080/00295639.2024.2347696

Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors

Alejandro Campos-Muñoz, Victor Hugo Sanchez-Espinoza, Elena Redondo-Valero, Cesar Queral

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S777-S796

Research Article / dx.doi.org/10.1080/00295639.2024.2357953

Development and Verification of Sampling Code NECP-SOUL for Evaluated Nuclear Data Files in ENDF-6 Format

Tiejun Zu, Yihan Huang, Liangzhi Cao, Hongchun Wu

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S765-S776

Research Article / dx.doi.org/10.1080/00295639.2024.2364471

Analysis of Fission Matrix Databases with Nonuniform Fuel Temperature Profiles for Static and Transient Calculations

Maximiliano Dalinger, William Walters

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S754-S764

Research Article / dx.doi.org/10.1080/00295639.2024.2328944

Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA

Mark R. Gilbert

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S744-S753

Research Article / dx.doi.org/10.1080/00295639.2024.2342506

A Parametric Study for Convergence Improvement of the Ronen Method Through the DAAREM Algorithm

Johan Cufe, Daniele Tomatis

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S730-S743

Research Article / dx.doi.org/10.1080/00295639.2024.2392927

Study of the Accuracy of the Ronen Method at Material Interfaces

Johan Cufe, Daniele Tomatis

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S710-S729

Research Article / dx.doi.org/10.1080/00295639.2024.2333088

Impact of Modeling Assumptions on Muon Scattering Images of Loaded Dry Storage Casks

Julia Niedermeier, Maik Stuke

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S697-S709

Research Article / dx.doi.org/10.1080/00295639.2024.2340142

Parametric Sensitivity Analysis of Stability Margins of Holos-Quad Microreactor

Shai Kinast, Dean Price, Claudio Filippone, Brendan Kochunas

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S680-S696

Research Article / dx.doi.org/10.1080/00295639.2024.2352661

Fixed Source Sensitivity Calculations for Inertial Confinement Fusion Applications

Colin A. Weaver, Christopher M. Perfetti, Michael E. Rising

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S797-S807

Research Article / dx.doi.org/10.1080/00295639.2024.2380607

A Diffusion Scale Approximation for Stochastic Fission Chains with State Feedback

Chen Dubi, Anil K. Prinja

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S649-S663

Research Article / dx.doi.org/10.1080/00295639.2024.2324532

Prototyping of a Machine Learning–Based Burnup Measurement Capability for Pebble Bed Reactor Fuel

Nick Rollins, India Allan, Jason Hou

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S630-S648

Research Article / dx.doi.org/10.1080/00295639.2024.2328937

Recovering From Structural Instability in Nuclear Power Design Optimization

Dominic J. Brennan, Geoffrey T. Parks

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S617-S629

Research Article / dx.doi.org/10.1080/00295639.2024.2306707

Classification and Location of Neutron Noise Perturbations Using Convolutional Neural Networks

Mónica Chillarón, Antoni Vidal-Ferràndiz, Vicente Vidal, Gumersindo Verdú

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S606-S616

Research Article / dx.doi.org/10.1080/00295639.2024.2357395

Securing Anomaly Detection for Process-Based Time Series

Tyler Lewis, Arvind Sundaram, Ahmad Y. Al Rashdan, Hany S. Abdel-Khalik

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S587-S605

Research Article / dx.doi.org/10.1080/00295639.2024.2360313

Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors

G. Aversano, H. S. Parrilla, D. Hellfeld, J. R. Vavrek

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S575-S586

Research Article / dx.doi.org/10.1080/00295639.2024.2347686

Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks

Ronald Daryll E. Gatchalian, Pavel V. Tsvetkov

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S551-S574

Research Article / dx.doi.org/10.1080/00295639.2024.2328957

Predicting Model Biases of the APOLLO3 Neutronics Code Using Machine Learning: Toward a Multiscale and Multifidelity Approach

Claire Terrazzoni, Laurent Buiron, Jean-Marc Palau

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S537-S550

Research Article / dx.doi.org/10.1080/00295639.2024.2329837

Uncertainty Benchmarks for Time-Dependent Transport Problems

W. Bennett, R. G. McClarren

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S808-S817

Research Article / dx.doi.org/10.1080/00295639.2024.2333092

GEAR-MC and Differential-Operator Methods Applied to Electron-Photon Transport in the Integrated TIGER Series

Mekiel Olguin, Christopher Perfetti, Brian Franke, Aaron Olson

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S818-S827

Research Article / dx.doi.org/10.1080/00295639.2025.2462893

Sensitivity Analysis and Uncertainty Quantification on Point Defect Kinetics Equations with Perturbation Analysis

Miaomiao Jin, Jilang Miao

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S828-S835

Research Article / dx.doi.org/10.1080/00295639.2024.2364455

On the Assumptions Behind Statistical Sampling: A 235U Fission Yield Uncertainty Propagation Case Study

Enrica Belfiore, Federico Grimaldi, Luca Fiorito, Pablo Romojaro, Gašper Žerovnik, Pierre-Etienne Labeau, Sandra Dulla

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S836-S857

Research Article / dx.doi.org/10.1080/00295639.2024.2323217

Assessment of CFD Predictions Using Experiments from a Heated Gas-Cooled Pebble Bed Facility

K. Podila, Q. Chen, N. Onder

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S858-S880

Research Article / dx.doi.org/10.1080/00295639.2024.2356418

Taillefer—A Tool for Sensitivity Analysis and Uncertainty Propagation Studies for Steady-State Thermal-Hydraulic Simulations of Involute Fuel Element Research Reactors

Ronja Schönecker, Paolo Bianchini, Frederic Thomas, Yoann Calzavara, Winfried Petry, Christian Reiter

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S881-S897

Research Article / dx.doi.org/10.1080/00295639.2024.2340141

ARIANT Assessments for CANDU Analysis Using RD-14M Experiments

John Cui, Geoffrey Waddington, Shujun Wang, Songyu Liu

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S898-S922

Research Article / dx.doi.org/10.1080/00295639.2024.2380628

A Numerical Simulation of Steam Explosion in Preflooded Cavity During a Severe Accident Using the STAR-CCM+ Code

Jeong-Hyeon Eom, Gi-Young Tak, In-Sik Ra, Ji-Won Choi, Hae-Yong Jeong

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S923-S940

Research Article / dx.doi.org/10.1080/00295639.2025.2456373

A Survey of Multimaterial Treatments for Thermal Radiative Transfer

Quincy Huhn, Ben C. Yee, Andrew T. Till

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S941-S953

Research Article / dx.doi.org/10.1080/00295639.2024.2347688

Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow

Kristel Ghoos, Lukas Zavorka, Joseph Tipton, Igor Remec

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S954-S965

Research Article / dx.doi.org/10.1080/00295639.2024.2383099

New RMC Energy Deposition Treatment and its Application in Multi-Physics Simulation

Hao Luo, Kaiwen Li, Nan An, Shanfang Huang, Kan Wang

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S966-S986

Research Article / dx.doi.org/10.1080/00295639.2024.2316955

ORCA: A Tool for Radiological Consequences for Accidental Releases

P. Maka, E. Van Heerden, M. Rezaee

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S987-S993

Research Article / dx.doi.org/10.1080/00295639.2024.2315905

Coupled Neutronics-Thermal-Hydraulic Modeling of a Molten Salt Reactor: The Aircraft Reactor Experiment

François Martin, André Bergeron, Guillaume Campioni, Yannick Gorsse, Nathan Greiner, Elsa Merle

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S994-S1005

Research Article / dx.doi.org/10.1080/00295639.2024.2328964

Examining the Contributions of Various Source Layers and Transport Pathways to Dose Rates Exterior to a Low- and Intermediate-Level Radioactive Waste Storage Facility Using ADVANTG/MCNP

Bo-Lun Lai, Szu-Li Chang, Rong-Jiun Sheu

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S1006-S1015

Note / dx.doi.org/10.1080/00295639.2024.2318834

Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor

Santiago Bazzana, Juan I. Beliera, Dumitru Serghiuta, Alexandre Trottier

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S1016-S1030

Note / dx.doi.org/10.1080/00295639.2024.2331906

An Analysis of a Coarse-Group Subgroup Method Based on the Physical Probability Tables in APOLLO3®

Emeline Rosier, Li Mao, Richard Sanchez, Luiz Leal, Igor Zmijarevic

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S121-S134

Research Article / dx.doi.org/10.1080/00295639.2024.2340143

Symmetry Determining Equations and Lie Groups of the Neutron Transport Equation

Patrick F. O’Rourke, Scott D. Ramsey

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S264-S294

Research Article / dx.doi.org/10.1080/00295639.2024.2343119

Probability of Initiation in Coupled Multiplying Assemblies

Anil K. Prinja, Patrick F. O’Rourke, Scott D. Ramsey

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S249-S263

Research Article / dx.doi.org/10.1080/00295639.2024.2340167

On the Application of the Nyström Method to Two-Dimensional Neutral Particle Transport Problems in Heterogeneous Media

Gustavo A. Lorensi, Leonardo R. C. Moraes, Richard Vasques, Esequia Sauter, Fábio S. de Azevedo

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S235-S248

Research Article / dx.doi.org/10.1080/00295639.2024.2342498

A Stochastic Calculus Approach to Boltzmann Transport

J. Darby Smith, Rich Lehoucq, Brian Franke

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S220-S234

Research Article / dx.doi.org/10.1080/00295639.2024.2350086

Diffusion Limit–Preserving Lumped DFEMs on AMR Meshes

A. Till

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S201-S219

Research Article / dx.doi.org/10.1080/00295639.2024.2400437

On the Root Structure of the Coupled Assembly Probability of Initiation Equations

Patrick F. O’Rourke, Anil K. Prinja, Scott D. Ramsey

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S180-S200

Research Article / dx.doi.org/10.1080/00295639.2024.2439227

A Multilevel Approach for Direct Core Calculation Schemes

Antonio Galia

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S153-S179

Research Article / dx.doi.org/10.1080/00295639.2024.2329838

Development of NEMESI: A Multiparameter Library Generator Prototype for Industrial VVER and PWR Applications Based on APOLLO3®

A. Brighenti, B. Vezzoni, A. Hebert, B. Calgaro, E. Y. Garcia-Cervantes, G. Huaccho Zavala, L. Graziano, P. Laurent, L. Mercatali, P. Mosca, A. Previti, S. Santandrea, J. F. Vidal, A. Willien, I. Zmijarevic

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S135-S152

Research Article / dx.doi.org/10.1080/00295639.2024.2340161

Efficient and Portable Vectorized Sweep Kernels for the Transport Equation on 3D Cartesian Grids Using the Kokkos Framework

Gabriel Suau, Ansar Calloo, Rémi Baron, Romain Le Tellier

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S295-S311

Research Article / dx.doi.org/10.1080/00295639.2024.2340173

Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code

Arthur Le Bars, Andrea Gammicchia, Simone Santandrea

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S105-S120

Research Article / dx.doi.org/10.1080/00295639.2024.2328962

High-Precision Benchmarks for the Stochastic Rod

Eugene d’Eon, Anil Prinja

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S93-S104

Research Article / dx.doi.org/10.1080/00295639.2024.2420539

Resonance Calculation of FCM Fuel Based on the Global-Local Method

Siyu Yi, Zhouyu Liu, Kunpeng Wang, Wei Shen, Tiejun Zu, Liangzhi Cao, Hongchun Wu

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S73-S92

Research Article / dx.doi.org/10.1080/00295639.2023.2296239

Uncertainty Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA

Luca Fiorito, Matteo Zanetti, Federico Grimaldi, Gert van den Eynde

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S56-S72

Review Article / dx.doi.org/10.1080/00295639.2024.2353987

High-Fidelity Simulation of the Empire Microreactor Benchmark Problem Using Griffin with Online Cross Section Generation

Changho Lee, Hansol Park, Yeon Sang Jung, Cooper Trucks

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S42-S55

Review Article / dx.doi.org/10.1080/00295639.2024.2348855

Axial Power Distribution Using Improved Axial Reflector Constants Calculation

A. Rispo, X. Doligez, S. Ravaux, C. Trakas

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S31-S41

Review Article / dx.doi.org/10.1080/00295639.2024.2340184

APOLLO3®: Overview of the New Code Capabilities for Reactor Physics Analysis

P. Mosca, L. Bourhrara, A. Calloo, A. Gammicchia, F. Goubioud, L. Mao, F. Madiot, F. Malouch, E. Masiello, F. Moreau, S. Santandrea, D. Sciannandrone, I. Zmijarevic, E. Y. Garcia-Cervantes, G. Valocchi, J. F. Vidal, F. Damian, P. Laurent, A. Willien, A. Brighenti, L. Graziano, B. Vezzoni

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S17-S30

Review Article / dx.doi.org/10.1080/00295639.2024.2334992

Improvements to the Baff-Refl Equivalence Technique Applied to Reflector Models in PWRs

Sami Machach, Alain Hébert, Aldo Dall’Osso

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S1-S16

Review Article / dx.doi.org/10.1080/00295639.2024.2328451

Three-Dimensional Full-Core BEAVRS Using OpenMOC with Transport Equivalence

G. Giudicelli, B. Forget, K. Smith

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S312-S324

Research Article / dx.doi.org/10.1080/00295639.2024.2321661

Monte Carlo Source Convergence Diagnosis Method and Thermal-Physics Coupling Method Based on Functional Expansion Tallies

Nan An, Xiaoyu Guo, Hao Luo, Zhaoyuan Liu, Kan Wang

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S325-S341

Research Article / dx.doi.org/10.1080/00295639.2024.2363575

Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM

Axel Laureau, Thibault Le Meute, Thomas Ligonnet, Elsa Merle

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S342-S354

Research Article / dx.doi.org/10.1080/00295639.2024.2357422

A Generic Implementation of the D1S Methodology for Dose Rate Assessment by Monte Carlo Codes in Fusion Applications

Yannick Peneliau, Jonathan Dufour

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S355-S367

Research Article / dx.doi.org/10.1080/00295639.2024.2342496

Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations

Young In Kim, Hyung Jin Shim

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S368-S380

Research Article / dx.doi.org/10.1080/00295639.2024.2332003

Mitigating Spatial Error in the Iterative Quasi–Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering and Fission Rate Tallies

Samuel Pasmann, Ilham Variansyah, C. T. Kelley, Ryan G. McClarren

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S381-S396

Research Article / dx.doi.org/10.1080/00295639.2024.2332007

MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE

G. Giudicelli, R. Crowder, L. Harbour, D. Gaston

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S397-S405

Research Article / dx.doi.org/10.1080/00295639.2024.2332009

Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®

Alexis Jinaphanh, Giorgio Valocchi, Andrea Zoia

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S406-S434

Research Article / dx.doi.org/10.1080/00295639.2024.2323225

Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations

Benjamin R. Murphy, Christopher M. Perfetti

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S435-S450

Research Article / dx.doi.org/10.1080/00295639.2024.2332010

Monte Carlo Workflow Unification for Nuclear Reactor Analysis with Metamodel-Driven Modeling

Peter J. Kowal, Kurt A. Dominesey, Camden E. Blake, Robert A. Lefebvre, Forrest B. Brown, Wei Ji

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S451-S484

Research Article / dx.doi.org/10.1080/00295639.2024.2395172

Simulation of Neutron Multiplicity Counting Based on Monte Carlo Code RMC

Yuanhao Gou, Conglong Jia, Zhaoyuan Liu, Kan Wang

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S485-S499

Research Article / dx.doi.org/10.1080/00295639.2024.2380613

The Use of Variance Reduction Techniques for Photon Dose Estimation in the Design of Radiotherapy Facilities at 10 and 15 MeV via Monte Carlo Simulations

C. Fedon, R. P. Kollaard, A. Metz

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S500-S506

Research Article / dx.doi.org/10.1080/00295639.2024.2357435

Probability Density Functions with Correlations of Experimental and Evaluated 235U(nth,f) Fission Yields and Their Impacts on Reactivity Loss with Burnup

S. M. Cheikh, G. Kessedjian, D. Bernard, O. Serot, A. Chebboubi

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S507-S520

Research Article / dx.doi.org/10.1080/00295639.2024.2347693

High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS

Thomas Ligonnet, Axel Laureau, Andreas Pautz, Vincent Lamirand

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S521-S530

Research Article / dx.doi.org/10.1080/00295639.2024.2357963

Experimental Covariance Determination for Critical Integral Experiments

Eric Aboud, Jesse Norris, Daniel Siefman

Nuclear Science and Engineering / Volume 199 / Number 1S / April 2025 / Pages S531-S536

Research Article / dx.doi.org/10.1080/00295639.2024.2328452

 

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