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Volume 211

Number 1 | Number 2 | Number 3

Number 1

Reconstruction of γ Dose Rate Field and Algorithm Validation Based on Inverse Distance Weight Interpolation

Biao Zhang, Jinjia Cao, Shuang Lin, Yingming Song

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 1-12

Research Article / dx.doi.org/10.1080/00295450.2024.2312026

Startup and Multiphysics Analysis of a Compact kW-Class Thermal Spectrum Microreactor

Vedant K. Mehta, Aditya P. Shivprasad, Dasari V. Rao

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 13-31

Research Article / dx.doi.org/10.1080/00295450.2024.2312483

Experimental Study on Combustion Characteristics of Solvent and Fire Behavior During a Solvent Fire at Nuclear Fuel Cycling Facility

Hongchao Sun, Yiren Lian, Guoqiang Li, Lei Chen, Dongyuan Meng, Shutang Sun, Dajie Zhuang, Jiangang Zhang

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 32-38

Research Article / dx.doi.org/10.1080/00295450.2024.2312723

Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides

John N. Hamawi, Pedro B. Pérez

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 39-53

Research Article / dx.doi.org/10.1080/00295450.2024.2315362

Sparse-View Neutron Computed Tomography 3-D Reconstruction via the Fast Gradient Projection Algorithm

Tengfei Zhu, Yang Liu, Xiaoping Ouyang

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 54-65

Research Article / dx.doi.org/10.1080/00295450.2024.2318049

Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool

Roberto E. Fairhurst-Agosta, Tomasz Kozlowski

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 66-78

Research Article / dx.doi.org/10.1080/00295450.2024.2319922

Progress in Fast Modular Reactor Conceptual Design

Hangbok Choi, John Bolin, Oscar Gutierrez, Radu Curiac, Mohammad Alavi, Matthew Virgen, Ed Chin, James Beaver, Pascal Brocheny, Geoffrey Beausoleil, Abdellatif M. Yacout, Sal Rodriguez, Michael Corradini, Daejong Kim, Steven L. Krahn, Eric Thornsbury

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 79-92

Research Article / dx.doi.org/10.1080/00295450.2024.2319925

Development of a New Correlation for Saturated Flow Boiling Heat Transfer in a Helically Coiled Tube

Min Gi Kim, Byongjo Yun, Jae Jun Jeong

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 93-110

Research Article / dx.doi.org/10.1080/00295450.2024.2319926

Modified Evaporation Model for ATHLET System Code in a Passive Containment Cooling System for Nuclear Safety

Michel Haag, Iurii Dolganov, Stephan Leyer

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 111-126

Research Article / dx.doi.org/10.1080/00295450.2024.2319933

PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations

Djillali Saad, Mohamed Elhadi Boulheouchat, Mohamed Bouaouina, Tahar Zidi

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 127-142

Research Article / dx.doi.org/10.1080/00295450.2024.2323226

Evaluation of Reaction Rate Distribution for Shielding Region in the Prototype Fast Reactor Monju

Tetsuya Mouri, Taira Hazama, Hiroki Katagiri, Kazuya Ohgama

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 143-160

Research Article / dx.doi.org/10.1080/00295450.2024.2323228

Verification and Validation of Spectral Element Code for Supercritical CO2 Flow in Vertical Heated Tubes

Haomin Yuan, Tri Nguyen, Elia Merzari, Dillon Shaver, Ananias Tomboulides

Nuclear Technology / Volume 211 / Number 1 / January 2025 / Pages 161-183

Research Article / dx.doi.org/10.1080/00295450.2024.2323229

Number 2

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

Number 3

Two-Fluid and Discrete Population Balance Model for Simulation of Batch Sedimentation Relevant to Plutonium Reconversion

Saroj Kumar Panda, Panantharayil Vishnu Anand, Vivek Kumar Mishra, Ramachandran Pillai Rajeev, Konda Athmaram Venkatesan, Krishnamurthy Ananthasivan

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 377-399

Research Article / dx.doi.org/10.1080/00295450.2024.2326714

Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface

Mohamed S. El-Genk, Timothy M. Schriener

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 400-428

Research Article / dx.doi.org/10.1080/00295450.2024.2329830

Combustion Properties of Glove-Box Panel Resins Under Fire Accidents

Shinsuke Tashiro, Gunzo Uchiyama, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Koji Watanabe, Hitoshi Abe, Yuichi Yamane

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 429-438

Research Article / dx.doi.org/10.1080/00295450.2024.2329832

Calculation and Discussion for Crack Driving Force of Dissimilar Metal Welded Joint of Nuclear Power Equipment Nozzle and Safe End

Dasheng Wang, Jin Ting, Xu Xiao, Tan Jianping, Zhang Kun, Wang Guozhen

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 439-451

Research Article / dx.doi.org/10.1080/00295450.2024.2329833

Flow Regime Classification in Hexagonal Wire-Wrapped Fuel Assembly Using Advanced Machine Learning Models

Hansol Kim, Joseph Seo, Yassin Hassan

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 452-475

Research Article / dx.doi.org/10.1080/00295450.2024.2331897

Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR

M. W. Abdulrahman

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 476-499

Research Article / dx.doi.org/10.1080/00295450.2024.2337234

Feasibility Analysis of Tritium Measurement in the Aqueous Medium Based on a Plastic Scintillating Fiber Array

Wenyu Cheng, Linlin Zeng, He Zhou, Jie Liang, Ke Deng, Qin Zhang, Wei Liu

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 500-512

Research Article / dx.doi.org/10.1080/00295450.2024.2338508

Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections

Michal Cibula, Marco Pellegrini, Masato Mizokami, Shinya Mizokami

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 513-530

Research Article / dx.doi.org/10.1080/00295450.2024.2339578

Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator

Hossam H. Abdellatif, Palash K. Bhowmik, David Arcilesi, Piyush Sabharwall

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 531-547

Research Article / dx.doi.org/10.1080/00295450.2024.2342168

Methodology for Multiparameter Evaluation of Barriers Against Proliferation of Minor Actinides

Markus Preston, Erik Branger, Vitaly Fedchenko, Sophie Grape, Robert E. Kelley, Vaibhav Mishra, Débora M. Trombetta

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 548-569

Research Article / dx.doi.org/10.1080/00295450.2024.2342184

Development of a Potential Facility Risk Index for Nuclear Safety and Security Using a Terrorism Scenario with a Hypothetical Nuclear Facility

Joeun L. Kot, Theodore Thomas, Jason T. Harris

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 570-583

Research Article / dx.doi.org/10.1080/00295450.2024.2343971

Failure Analysis of CRDINiCr Butterfly Valves for Nuclear Power Plant Applications

Jian Cheng, Kewei Fang, Kexun Fei, Qiang Wang, Bo Li, Eduardo B. Farfán

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 584-597

Research Article / dx.doi.org/10.1080/00295450.2024.2344912

Determination of Airborne Release Fractions from Loose Powder Contamination Under Impact Stress

Mellissa Komninakis, Joseph Sinicrope, James C. Nicholson, Philip Moore, Yolanda Rodriguez, Leonel Lagos, Daniela Radu

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 598-606

Research Article / dx.doi.org/10.1080/00295450.2024.2345945

Prolonged Operation of Hydro-Accumulators in VVER-1000/V446 Considering Flow Restriction Components

Seyed Ali Hosseini, Alireza Najafi, Amir Saeed Shirani, César Queral, Francesco D’Auria

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 607-623

Note / dx.doi.org/10.1080/00295450.2024.2337313

Surface-Activated Graphite Oxide Nanosheets with Promoted U(VI) Adsorption Performance

Jianwei Zhang, Tuo Li, Bo Tian, Jinfeng Li, Wenze Li, Abdullah, Nan Zhang, Hongtao Zhao

Nuclear Technology / Volume 211 / Number 3 / March 2025 / Pages 624-634

Note / dx.doi.org/10.1080/00295450.2024.2343116

 

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