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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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State legislation: Illinois bill aims to lift state’s remaining nuclear moratorium
A bill that would fully repeal the state’s entire moratorium on new nuclear projects survived a key deadline in the Illinois General Assembly last week.
To stay afloat in the spring legislative session, bills needed to be assigned to committee by March 21, and state Sen. Sue Rezin’s Senate Bill 1527 now sits with the Senate’s Energy and Public Utilities committee for review.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2024.2323229
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2024.2326375
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.1080/00295450.2024.2343116
A Review on the Development of Single-Moderator-Based Neutron Spectrometers
Rasito Tursinah, Sidik Permana, Zaki Su’ud, Alan Maulana, Putu Sukmabuana
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 635-644
Review Article | doi.org/10.1080/00295450.2024.2361177
Nonhomogeneous Poisson Process Model for Estimating Mean Time Between Failures of the JE01-AP03 Primary Pump Implemented on the RSG-GAS Reactor
Sri Sudadiyo
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 645-660
Review Article | doi.org/10.1080/00295450.2024.2352663
Safety Assessment Methodology for Transportation of Radioactive Material via Train
Manorma Kumar, Guillem Cortes Rossell
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 661-673
Review Article | doi.org/10.1080/00295450.2024.2356328
Validation of McCARD Monte Carlo Calculation Code Against NAA Experiments Using Rare Earth Element Certified Reference Material Activated at JRTR
Rashdan Malkawi, Sayel Marashdeh, Kafa Al-Khasawneh, Aseel Al-Mohammad, Mahmoud Suaifan, Mohammad Omari, Majd Hawwari
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 674-689
Research Article | doi.org/10.1080/00295450.2024.2346869
The Use of High-Density UN Fuel in Heat-Pipe Microreactors
Cihang Lu, Erofili Kardoulaki, Nicolas E. Stauff, Arantxa Cuadra
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 690-707
Research Article | doi.org/10.1080/00295450.2024.2348732
Electrochemical Identification of Metal Chlorides in Eutectic LiCl-KCl Without Prior Knowledge of Analyte Identities
Tyler Williams, Jason Torrie, Mark Schvaneveldt, Ranon Fuller, Greg Chipman, Devin Rappleye
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 708-724
Research Article | doi.org/10.1080/00295450.2024.2348849
Fluid Dynamics Effects of a Porous Blockage on Laminar Flow in the Interior Subchannels of a 61-Pin Wire-Wrapped Rod Bundle
Trevor Melsheimer, Craig Menezes, Yassin A. Hassan
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 725-741
Research Article | doi.org/10.1080/00295450.2024.2348853
Examining Low-Energy Gamma-Ray Protection of a New Cement Product as an Alternative Cementitious Material Using Geant4 Software
Muneerah A. Al-Aqeel
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 742-754
Research Article | doi.org/10.1080/00295450.2024.2355405
Investigation of the Thermal Effects of MgO and ZnO Nanoparticles in a Pressurized Water Reactor Coolant with Computational Fluid Dynamics Model
Sinem Uzun
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 755-767
Research Article | doi.org/10.1080/00295450.2024.2356331
Refueling Considerations for 99Mo Production in a CANDU Reactor
J. Haroon, E. Nichita
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 768-776
Research Article | doi.org/10.1080/00295450.2024.2357917
CHF Enhancement by γ-Fe2O3 Nanofluids with Pool Boiling Condition on a Downward-Facing Plane
Xintian Cai, Huai-En Hsieh, Zhibo Zhang, Shiqi Wang, Saikun Wang
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 777-789
Research Article | doi.org/10.1080/00295450.2024.2361180
Numerical Study of Porous Cylindrical Containment for the Fuel Element of a Centrifugal Nuclear Thermal Rocket
Pramatha Bhat, Kendall R. Adams, Stephen J. Herring, Brad Kirkwood
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 790-806
Research Article | doi.org/10.1080/00295450.2024.2361185
Investigation of Lunar Shallow Subsurface Water Content and Soil Elemental Composition via Active Neutron Detection
Huanyu Han, Xiaoyu Li, Zhi Chen
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 807-820
Research Article | doi.org/10.1080/00295450.2024.2361194
Discrete Element Method Simulation of Vibratory Filling of Convoluted Hot Isostatic Pressing Canisters Using Idaho Calcine Waste Simulant
Simon Chung, Martin Stewart, Peter Wypych, David Hastie, Andrew Grima, Sam Moricca
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 821-847
Research Article | doi.org/10.1080/00295450.2024.2361195
Discrete Element Method Simulation of the Idaho Calcine Simulant for Hot Isostatic Pressing Canister Filling Process: Part 2
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 848-861
Research Article | doi.org/10.1080/00295450.2024.2361190
