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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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!
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Mar 2025
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Nuclear Science and Engineering
April 2025
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Nuclear materials testing project brings U.S. and U.K. expertise together
As nations look to nuclear energy as a source of reliable electricity and heat, researchers and industry are developing a new generation of nuclear reactors to fill the need. These advanced nuclear reactors will provide safe, efficient, and economical power that go beyond what the current large light water reactors can do.
But before large-scale deployment of advanced reactors, researchers need to understand and test the safety and performance of the technologies—especially the coolants and materials—that make them possible.
Now, the United States and the United Kingdom have teamed up to test hundreds of advanced nuclear materials.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2024.2332021
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2024.2363089
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2024.2372516
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295639.2024.2384220
