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Volume 199

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Number 1

Dynamic Magnetic Field Analysis and Delivery Strategy Optimization for Scanning Magnet in Proton Therapy System

Xinyi Shen, Ping Tan, Xinze Wang, Songbin Chen, Haimin Xiong

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 1-17

Research Article / dx.doi.org/10.1080/00295639.2024.2340182

Experiments on Criticality and Reactivity Worths in the FCA-XXII-1 Assembly Simulating Highly Enriched MOX Fueled Tight Lattice LWR Cores

Masahiro Fukushima, Masaki Andoh, Yasunobu Nagaya

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 18-41

Research Article / dx.doi.org/10.1080/00295639.2024.2347706

Reaction Rate Ratios for Recent Fast Metal Experiments with Large Plutonium Masses

Jesson Hutchinson, Jennifer Alwin, Theresa Cutler, Matthew Gooden, Noah Kleedtke, Denise Neudecker, Nicholas Thompson, Robert Weldon, Nicholas Whitman, Robert Little

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 42-60

Research Article / dx.doi.org/10.1080/00295639.2024.2343118

A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors

Lixun Liu, Han Zhang, Xinru Peng, Qinrong Dou, Yingjie Wu, Jiong Guo, Fu Li

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 61-81

Research Article / dx.doi.org/10.1080/00295639.2024.2344956

Hot Hydrogen Testing of W-Coated UN Kernels in a Mo30W Matrix

Arne Cröll, Jamelle K. P. Williams, Brian Taylor, Martin P. Volz, Christopher McKinney, Timothy Coons, Jhonathan Rosales

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 82-99

Research Article / dx.doi.org/10.1080/00295639.2024.2332001

Combining Similarity Measures and Left-Right Hidden Markov Models for Prognostics of Items Subjected to Perfect and Imperfect Maintenance

Mattia Zanotelli, J. Wesley Hines, Jamie B. Coble

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 100-114

Research Article / dx.doi.org/10.1080/00295639.2024.2303165

Simulating Fuel Assembly Bowing: A Neutron-Diffusion Method Based on Arbitrary Quadrilateral Node and Conformal Mapping Technique

Hongchun Wu, Lin Guo, Chenghui Wan

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 115-130

Research Article / dx.doi.org/10.1080/00295639.2024.2334988

Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces

Jiyu Zheng, Liang Zhang, Zheng Liang, Bojia Wei, Zhongchao Yan, Xin Chen

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 131-150

Research Article / dx.doi.org/10.1080/00295639.2024.2340145

Age Dating of Repurified and Mixed Plutonium Using Machine Learning

Michael Pietrykowski, Mark R. Scott

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 151-161

Research Article / dx.doi.org/10.1080/00295639.2024.2344957

Self-Healing Control of Nuclear Power Plants Under False Data Injection Attacks

Stephen Yoo, Greg Mohler, Fan Zhang

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 162-175

Research Article / dx.doi.org/10.1080/00295639.2024.2372520

On the Possibility of Achieving Optimal Operating Modes of Hyperspeed Model Gas Centrifuges: 3D Numerical Simulation

S. V. Bogovalov, I. V. Tronin, A. V. Vasilyev

Nuclear Science and Engineering / Volume 199 / Number 1 / January 2025 / Pages 176-183

Research Article / dx.doi.org/10.1080/00295639.2024.2332021

Number 2

Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels

W. A. Metwally, M. N. Dupont, W. J. Marshall, C. Celik, V. Karriem, A. Lang, K. L. Fassino, A. M. Shaw

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 185-193

Review Article / dx.doi.org/10.1080/00295639.2024.2360309

On the Accuracy of Transport Spatial Discretization Methods for Diffusive Regimes

Rodolfo M. Ferrer, Edward W. Larsen

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 194-208

Research Article / dx.doi.org/10.1080/00295639.2024.2356986

Thermal Release Mechanisms of a Typical Absorber at the Synchrotron Radiation Front End Based on Finite Element Analysis

Yunfei Sun, Tong Li, Lan Lan, Shuhao Xu, Jiahua Chen, Wanqian Zhu, Song Xue, Hongxin Luo, Limin Jin

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 209-222

Research Article / dx.doi.org/10.1080/00295639.2024.2356400

A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations

T. L. Gordon, M. M. R. Williams, M. D. Eaton

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 223-238

Research Article / dx.doi.org/10.1080/00295639.2024.2348859

In Situ Electronic Structure Analysis of Water-Corroded UNx in High Vacuum

Zhilei Chen, Huoping Zhong, Yin Hu, Tingwen Yan, Ruilong Yang, Qifa Pan, Lizhu Luo, Yongbin Zhang, Daoming Chen, Kezhao Liu

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 239-252

Research Article / dx.doi.org/10.1080/00295639.2024.2348856

The Q-cascade Theory with Material Losses and Gains

Shi Zeng

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 253-265

Research Article / dx.doi.org/10.1080/00295639.2024.2347730

Practical Design of a Breed-and-Burn Lead-Cooled Fast Reactor with Rotational Fuel Shuffling Strategy

Alexandru Catalin Stafie, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 266-279

Research Article / dx.doi.org/10.1080/00295639.2024.2347716

Verification of Adjoint Solution Commutativity with the New OpenNode Nodal Diffusion Code

Hicham Satti, Otman El Hajjaji, Tarek El Bardouni, Tarik El Ghalbzouri

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 280-294

Research Article / dx.doi.org/10.1080/00295639.2024.2357454

Review and Modeling of Integrated Energy Systems with Nuclear Reactor Coupled Desalination and District Heating

Md Akhlak Bin Aziz, C. T. Callaway, Nicholas R. Brown, Caleb Brooks

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 295-313

Research Article / dx.doi.org/10.1080/00295639.2024.2357394

Examining Beam Matching in the Commissioning of a Halcyon Accelerator

Duong Thanh Tai, Hoang Duc Tuan, Nguyen Xuan Hai, Nguyen Ngoc Anh, David Bradley, Peter Sandwall, James C. L. Chow

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 314-324

Research Article / dx.doi.org/10.1080/00295639.2024.2366733

A Modified Implicit Monte Carlo Method for Frequency-Dependent Three Temperature Radiative Transfer Equations

Min Gao, Yi Shi

Nuclear Science and Engineering / Volume 199 / Number 2 / February 2025 / Pages 325-337

Note / dx.doi.org/10.1080/00295639.2024.2363089

Number 3

Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 235U

H. Naik, S. P. Dange, R. J. Singh, W. Jang

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 339-357

Research Article / dx.doi.org/10.1080/00295639.2024.2372514

A System Predictive Maintenance Framework for Advanced Reactors Using a Data-Driven Digital Twin

Andy Rivas, Gregory Kyriakos Delipei, Jason Hou

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 358-387

Research Article / dx.doi.org/10.1080/00295639.2024.2372515

A Characteristics Approach to the Finite Element Method

Adam Q. Lam, Richard M. Vega

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 388-409

Research Article / dx.doi.org/10.1080/00295639.2024.2380611

Charge Distribution Studies in the Epi-Cadmium Neutron-Induced Fission of 241Pu

H. Naik, R. J. Singh, S. P. Dange, W. Jang

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 410-428

Research Article / dx.doi.org/10.1080/00295639.2024.2371748

Uncertainty Quantification of 237Np, 241Am, and 243Am Reaction Rates in Highly Enriched Uranium Fuel Cores at Kyoto University Critical Assembly

Cheol Ho Pyeon, Akito Oizumi, Ryota Katano, Masahiro Fukushima

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 429-444

Research Article / dx.doi.org/10.1080/00295639.2024.2380624

Uncertainty-Based Validation Methodology and Experimental Analysis for External Control Room Human Performance Simulation: Application to Fire Probabilistic Risk Assessment of Nuclear Power Plants

Mohammad Albati, Tatsuya Sakurahara, Seyed Reihani, Ernie Kee, Jaemin Yang, Terry von Thaden, Richard Kesler, Farzaneh Masoud, Zahra Mohaghegh

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 445-464

Research Article / dx.doi.org/10.1080/00295639.2024.2366735

Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery

Shiping Wei, Yuyao Wei, Jin Wang, Shaojian Yan, Wei Wang, Zhixin Ma, Chunjing Li

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 465-475

Research Article / dx.doi.org/10.1080/00295639.2024.2368993

Investigation and Analysis of Beta Radioisotopes for Optimal Use in Betavoltaic Batteries

D. Ghasemabadi, H. Zaki Dizaji, M. Abdollahzadeh

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 476-489

Research Article / dx.doi.org/10.1080/00295639.2024.2370675

Analytical Prediction of Temperature Distribution in a Deep Geological Nuclear Waste Repository

Xiangyun Zhou, Shixiang Hu, Weiding Zhuo, Long Wang, De’An Sun, Luqiang He, You Gao, Xiayang Zhang

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 490-505

Research Article / dx.doi.org/10.1080/00295639.2024.2372513

Numerical Investigation of Air Natural Convection in the AP1000 Passive Containment Cooling System Following LBLOCA Using ANSYS FLUENT

Hossam H. Abdellatif, David Arcilesi

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 506-517

Research Article / dx.doi.org/10.1080/00295639.2024.2375174

A Multi-Objective Optimization Design for Enhancing Space Utilization and Minimizing Cutting Time in Nuclear Facility Component Decommissioning

Wanyi Tian, Yanfei Zhang, Weiwei Chen, Junhao Zhang, Bingyu Ni, Chao Jiang

Nuclear Science and Engineering / Volume 199 / Number 3 / March 2025 / Pages 518-529

Research Article / dx.doi.org/10.1080/00295639.2024.2372516

Number 4

Corrosion of EP823 Steel Cladding Under Heavy-Liquid-Metal-Coolant Reactor Conditions: A Review

Rafael Isayev, Natalia Pukhareva, Evgeniy Malinovskiy, Egor Korenevski, Pavel Dzhumaev

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 531-549

Review Article / dx.doi.org/10.1080/00295639.2024.2383110

Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p + 7Li Reaction

H. Kumawat

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 550-556

Review Article / dx.doi.org/10.1080/00295639.2024.2380636

Effect of Bi2O3/WO3 on Improving the Ability of Polyepoxide-Based Composites to Attenuate Gamma Rays

Mohamed Y. Hanfi, Mohammad W. Marashdeh, Sitah Alanazi, Mamduh J. Aljaafreh, Karem A. Mahmoud

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 557-568

Research Article / dx.doi.org/10.1080/00295639.2024.2383105

Preliminary Verification of Key Physical Models in Oxide Fuel Performance Analysis Code FEATURE Based on COMSOL

Rui Yu, Guan Wang, Wei Jiang, Yanlei Zhu, Changping Qin, Long Gu

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 569-577

Research Article / dx.doi.org/10.1080/00295639.2024.2384225

Effect of Angular Momentum–Dependent Transparency on the Neutron-Nucleus Cross Section

A. M. Alshamy, M. M. Musthafa

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 578-585

Research Article / dx.doi.org/10.1080/00295639.2024.2381397

Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor

Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 586-598

Research Article / dx.doi.org/10.1080/00295639.2024.2383102

A Second Moment Method for k-Eigenvalue Acceleration with Continuous Diffusion and Discontinuous Transport Discretizations

Zachary K. Hardy, Jim E. Morel, Jan I. C. Vermaak

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 599-612

Research Article / dx.doi.org/10.1080/00295639.2024.2384223

Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO2 Fuel

Gilles Youinou

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 613-630

Research Article / dx.doi.org/10.1080/00295639.2024.2381387

Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident

Zenghao Dong, Jianquan Liu, Xinyi Niu, Lihan Hai, Wenlong Zhou

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 631-652

Research Article / dx.doi.org/10.1080/00295639.2024.2381391

Vaporization in Liquid-Core Nuclear Thermal Rockets

Dakota Santana, D. Keith Hollingsworth

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 653-678

Research Article / dx.doi.org/10.1080/00295639.2024.2380633

Resolving the BWR Stability Paradox of Space-Dependent Decay Ratios

Yousef M. Farawila, Daniel R. Tinkler

Nuclear Science and Engineering / Volume 199 / Number 4 / April 2025 / Pages 679-697

Research Article / dx.doi.org/10.1080/00295639.2024.2384220

Number 5

The MUSIC Critical Benchmark and Nuclear Data

Alex McSpaden, Jesson Hutchinson, Michael Rising, Rene Sanchez, Nicholas Thompson, George McKenzie

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 699-724

Research Article / dx.doi.org/10.1080/00295639.2024.2384817

A Benchmark for Neutron Kinetics Methods in Hexagonal Geometry

William C. Dawn

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 725-735

Research Article / dx.doi.org/10.1080/00295639.2024.2396173

An Open-Source Coupling for Depletion During Fuel Cycle Modeling

Amanda M. Bachmann, Oleksandr Yardas, Madicken Munk

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 736-749

Research Article / dx.doi.org/10.1080/00295639.2024.2393940

Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method

Wei Xiao, Xiaojing Liu, Jianhua Zu, Xiang Chai, Hui He, Tengfei Zhang

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 750-771

Research Article / dx.doi.org/10.1080/00295639.2024.2394732

Uncertainty Propagation of Monte Carlo Cross-Section Generation for Graphite-Moderated Pebble Bed Reactors

Jin Li, Volkan Seker, Andrew Ward, Thomas Downar

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 772-792

Research Article / dx.doi.org/10.1080/00295639.2024.2397621

A “Consistent” Quasidiffusion Method for Solving Particle Transport Problems

Edward W. Larsen, Tomás M. Paganin, Richard Vasques

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 793-802

Research Article / dx.doi.org/10.1080/00295639.2024.2392942

Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties

He Xue, Rongxin Wang, Zheng Wang, Jun Wu, Miao Geng

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 803-816

Research Article / dx.doi.org/10.1080/00295639.2024.2393020

Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel-Cladding Chemical Interaction

Kookhyun Jeong, Yong Yang

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 817-828

Research Article / dx.doi.org/10.1080/00295639.2024.2389601

Development of Target Holder for the First Experiment on an Alternative Route for 64Cu Radioisotope Production by Secondary Neutron Irradiation of a 64ZnO Target

Imam Kambali, Angga Dwi Saputra, Marlina Marlina, Isdandy Rezki Febrianto, Ihwanul Aziz, Wira Y Rahman, Kristedjo Kurnianto, Rasito Tursinah, Rien Ritawidya, Ratna Dini Haryuni, Parwanto Parwanto, Rajiman Rajiman, Nur Huda, Kartika Fajarwati

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 829-837

Research Article / dx.doi.org/10.1080/00295639.2024.2392070

Research on Assessment Method for Cognitive Influence Factors of Nuclear Power Plant Operators Based on Fuzzy Analytic Hierarchy Process and Deep Learning of Electroencephalogram Signals

Dongliang Zhang, Jia Shi

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 838-853

Research Article / dx.doi.org/10.1080/00295639.2024.2397256

A New Galerkin Quadrature Method Not Requiring a Matrix Inverse

Emerson W. Shands, Jim E. Morel, Cory D. Ahrens, Brian C. Franke

Nuclear Science and Engineering / Volume 199 / Number 5 / May 2025 / Pages 854-871

Research Article / dx.doi.org/10.1080/00295639.2024.2385220

 

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