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Volume 199

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