ANS / Publications / Journals / Nuclear Technology

Fluid-Solid Interaction Analysis at the Slip Joint of a Boiling Water Reactor Type 5 Jet Pump

J. Cruz-Castro, L. H. Hernández-Gómez, Y. López-Grijalba, E. Hernández-Palafox, J. A. Beltrán-Fernández, J. I. E. Palacios-Hernández, I. A. Alarcón-Sánchez

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 185-199

Research Article / dx.doi.org/10.1080/00295450.2024.2323239

A Study on Boiling Heat Transfer Performance of TiO₂-CNTs Hybrid Nanofluid on a Downward-Facing Heating Surface

Songling Liu, Huai-En Hsieh, Shiqi Wang

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 200-213

Research Article / dx.doi.org/10.1080/00295450.2024.2323240

Theoretical Calculation of Gamma-Ray and Neutron Shielding Properties for CsPbBr₃-Polypropylene Composite Material

Junfeng Zhao, Yuanjie Sun, Yue Zhang, Zhigang Li, Hongtao Zhao, Qingyu Wang

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 214-224

Research Article / dx.doi.org/10.1080/00295450.2024.2323257

Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools

Zeyun Wu, Christian Pochron, Mihai (Mike) G. M. Pop, Neal Mann

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 225-240

Research Article / dx.doi.org/10.1080/00295450.2024.2323267

Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems

Sarah R. Suffield, William A. Perkins, Ben J. Jensen, Brady D. Hanson, Steven B. Ross

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 241-257

Research Article / dx.doi.org/10.1080/00295450.2024.2324213

Development and Verification of Neutron Kinetics Parameter Calculation Program Applicable to Subcritical Systems of Long-Life Reactors

Shikun Xu, Lingyi Qu, Tao Yu, Jinsen Xie, Ji Tong, Zining Ni, Nianbiao Deng, Hiroshi Watabe

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 258-272

Research Article / dx.doi.org/10.1080/00295450.2024.2324513

Mixing of Hydrogen-Steam Buoyancy Jets Released into the Upper Atmosphere of the Containment Building

Youngsu Na

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 273-285

Research Article / dx.doi.org/10.1080/00295450.2024.2325738

Effect of Cooling Pump Transient Power Supply on ETRR-2 Safety Parameters

Abdelfatah Abdelmaksoud, Asmaa Gamal, Ahmed R. Adly

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 286-297

Research Article / dx.doi.org/10.1080/00295450.2024.2325739

Development of Obligation Tracking System for Internationally Controlled Items in Accordance with Bilateral Nuclear Cooperation Agreements

Mun-Young Ryu, Hyun-Jo Kim, Jin-Ha Choi

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 298-317

Research Article / dx.doi.org/10.1080/00295450.2024.2325742

Novel Approach for Network Data Exchange Among Safety-Related Control Systems of Nuclear Reactors

Aditya Gour, R. P. Behera, Tom Mathews

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 318-331

Research Article / dx.doi.org/10.1080/00295450.2024.2325749

Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction

Zhenyu Wang, Zungang Wang, Jian Sun, Zhiyuan Li, Shanxue Xi, Xing Wei, Weiqi Huang, Chunzhi Zhou

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 332-343

Research Article / dx.doi.org/10.1080/00295450.2024.2325751

Evaluating Material Attractiveness of Minor Actinide Nuclear Fuel Intended for a Waste Transmutation Lead-Cooled Fast Reactor

Débora M. Trombetta, Erik Branger, Markus Preston, Sophie Grape

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 344-357

Research Article / dx.doi.org/10.1080/00295450.2024.2326374

Risk Plus Some Attributes (R + SA): A New Risk-Informed Method for Prioritizing Inspection Activities During New Fuel Facility Construction

Peter Yarsky, Kevin Coyne, Cynthia Taylor, Chad Oelstrom

Nuclear Technology / Volume 211 / Number 2 / February 2025 / Pages 358-376

Research Article / dx.doi.org/10.1080/00295450.2024.2326375