ANS / Publications / Journals / Nuclear Technology

Multiscale Modeling of the Mechanical Response of Silicon Carbide Composite Within the Accelerated Fuel Qualification Framework

George M. Jacobsen, Chris Ellis, Joel Kosmatka, Herbert Shatoff, Panto Mijatovic, Ricardo Lebensohn, Laurent Capolungo, Kevin Spilker, Kyle Gamble, Gyanender Singh, Jason Hales, Christina A. Back

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 1-19

Research Article / dx.doi.org/10.1080/00295450.2025.2480978

Role of Accelerated Burnup Irradiation Testing in Support of Accelerated Fuel Qualification

A. T. Nelson, D. Adorno Lopes, N. A. Capps, C. M. Petrie

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 20-49

Research Article / dx.doi.org/10.1080/00295450.2025.2481360

Accelerated Fuel Qualification of Fast Modular Reactor Fuel in a Thermal Reactor: Modeling and Simulation Paired with Irradiation Testing

Hangbok Choi, Jason Rizk, Sarah Oswald, Lucas Borowski, Jaclynn Unangst, Jonas Opperman, Christian Deck, Hesham Khalifa, Ron Faibish, Yinbin Miao, Soon Kyu Lee, Abdellatif M. Yacout, Christina A. Back

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 50-65

Research Article / dx.doi.org/10.1080/00295450.2025.2502283

FAST Irradiations, Postirradiation Examinations, and Modeling of U-Mo for Light Water Reactor Applications

Geoffrey Beausoleil, Sobhan Patnaik, Luca Capriotti, Randall Fielding, Bryon Curnutt, Nate Oldham, Andrew Bascom, Alexander Swearingen, Jacob Hirschhorn, Cynthia Adkins, Robert Mariani

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 66-82

Research Article / dx.doi.org/10.1080/00295450.2025.2536893

Utilization of AI/ML Technologies for Fuel Thermal-Hydraulic Methodology Development in Westinghouse

Emre Tatli, Yixing Sung, Alex Mace, Jun Liao, Jesse Fisher, James Spring, Zeses Karoutas, Scott Sidener

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 83-97

Research Article / dx.doi.org/10.1080/00295450.2025.2517463

Bayesian Calibration of UO₂ Creep Rates as a Tool for Accelerated Fuel Qualification

C. O. T. Galvin, A. Schneider, P. Robbe, M. W. D. Cooper, W. D. Neilson, A. Claisse, C. Matthews, T. A. Casey, K. Sargsyan, H. N. Najm, D. A. Andersson

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 98-125

Research Article / dx.doi.org/10.1080/00295450.2025.2505813

Mechanistic Multiscale Uncertainty Propagation in Support of Accelerated Fuel Qualification

Christopher Matthews, Michael W. D. Cooper, Pieterjan Robbe, Tiernan Casey, Khachik Sargsyan, Habib N. Najm, Giovanni Pastore, Sophie Blondel, Nick Militello, Brian Wirth, Alex Levinsky, Joshua White, Tammie Gibson, Christopher R. Stanek, David A. Andersson

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 126-138

Research Article / dx.doi.org/10.1080/00295450.2025.2505811

Enhanced Radiation Shielding and Structural Modifications in Samarium (III) Oxide-Reinforced Type 316L Stainless Steel Composites for Nuclear Applications: A Comprehensive Evaluation of Physical, Structural, Mechanical, Gamma-Ray, and Neutron Attenuation Properties

Nihal Yayla, M. Gökhan Albayrak, Ömer Güler, Duygu Sen Baykal, Hessa Alkarrani, Ghada ALMisned, H. O. Tekin

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 139-159

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2462483

Numerical Investigation of Changes in Heat Transfer Coefficient of Water-Aluminum Oxide Nanofluid Cooling in Nuclear Reactors

Mansur Mustafaoglu

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 160-178

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2462488

Effect of Boric Acid on Volatile Fission Products in Conditions Simulating a Severe Nuclear Accident

Fredrik Börjesson Sandén, Anna-Elina Pasi, Teemu Kärkelä, Tuula Kajolinna, Christian Ekberg

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 179-197

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2462490

Integrating Econometrics and Artificial Intelligence to Assess the Impact of Trade on Nuclear Proliferation

Chansuh Lee, Kyungtae Lim, Man-Sung Yim

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 198-218

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2462494

Development of a Flow Stabilization Algorithm Enabling Measurement of Low Oxygen Concentrations in Liquid Sodium

Dustin W. Mangus, Martin S. J. Dehon, Sophia R. S. Jones, Samuel A. Briggs, Wade R. Marcum, Guillaume P. H. Mignot

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 219-236

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2463813

Effect of Sintering on the Resuspension of Multilayer Graphite Particle Deposits in High-Temperature Gas-Cooled Reactors

Shumiao Zhao, Zhu Fang, Zhikai You, Xinxin Wu, Libin Sun, Yiyang Zhang

Nuclear Technology / Volume 212 / Number 1 / January 2026 / Pages 237-252

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2464420

Literature Review of Preliminary Initiating Events for a Gas-Cooled Fast Reactor Conceptual Design

Irfan Ibrahim, Megan Harkema, Steven Krahn, Hangbok Choi, John Bolin, Eric Thornsbury

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 253-276

Review Article / dx.doi.org/10.1080/00295450.2025.2472573

A Batch Refueling Framework for Implementing the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design

C. Erika Moss, Ondrej Chvala, Donny Hartanto, John P. Carter

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 277-293

Research Article / dx.doi.org/10.1080/00295450.2025.2464430

Development and Demonstration of a Prototype Molten Salt Sampling System

Megan Harkema, Steven Krahn, Paul Marotta, Adam Burak, Xiaodong Sun, Piyush Sabharwall

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 294-313

Research Article / dx.doi.org/10.1080/00295450.2025.2480982

Salt Spills Analysis Methodology for KP-FHR: Two-Phase Mechanical Aerosolization and Evaporation Mass Transfer

Kyoung M. Kang, Quan Zhou, Matthew Denman, Jake McMurray, Timothy Drzewiecki, Haihua Zhao

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 314-327

Research Article / dx.doi.org/10.1080/00295450.2025.2529714

Investigating the Role of Chromium-Coated Clad During Accident Progression for an SMR Using MELCOR

Mohammad Amer Allaf, Grace Ejnik, Emile Zaccomer, Woo Hyun Jung, Michael Corradini, Juliana Pacheco Duarte

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 328-346

Research Article / dx.doi.org/10.1080/00295450.2025.2505808

Assessment of Iodine Gas Decontamination in Sodium Pool for Advanced Reactors

Dong Hoon Kam, Dave Grabaskas, Yasushi Okano, Akihiro Uchibori, Tyler Starkus

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 347-364

Research Article / dx.doi.org/10.1080/00295450.2025.2507534

A Systematic Diagnostics and Enhancement Framework for Advancing Probabilistic Risk Assessment Tools

Egemen M. Aras, Arjun Earthperson, Mihai A. Diaconeasa

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 365-382

Research Article / dx.doi.org/10.1080/00295450.2025.2511510

Geopolymers as Emerging Materials for Immobilization of Toxic Radionuclides

Warda Ashraf, Mumtaz Khan, Sabriye Yusan, Muhammad Qasim, Niu Jie

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 383-394

Regular Review Article / dx.doi.org/10.1080/00295450.2025.2464426

Progress Toward Instrumented Nuclear Fuel Pellets Using Additive Manufacturing

D. A. Huston, A. Prasad, N. Kotsios, A. Bergeron, F. Kelly, E. C. Corcoran

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 395-409

Regular Review Article / dx.doi.org/10.1080/00295450.2025.2472094

Computational Framework for Estimating Cost of Equipment Disposal for Advanced Reactors

Chumani Mokoena, Koroush Shirvan

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 410-426

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2464424

A Reinforcement Learning Approach to Augment Conventional PID Control in Nuclear Power Plant Transient Operation

Aidan Rigby, Mike Wagner, Daniel Mikkelson, Ben Lindley

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 427-445

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2466137

Optimizing Layout of Key Chips of Nuclear Safety Control System to Reduce Working Temperature by Using Machine Learning

Fanyu Wang, Dongwei Wang, Qi Chen, Yang Zhao, Minjie Lei, Jinyu He

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 446-460

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2470025

Enhancing Site Evaluation Standards for Nuclear Power Plants in Indonesia: Human-Induced External Events

Siti Alimah, Khusnul Khotimah, Budi Santoso, Sriyono, Kurnia Anzhar, Chevy Cahyana, Agus Teguh Pranoto, Joko Waluyo, Rismiyanto, Hadi Suntoko, Sriyana, Fepriadi, Nicholas Bertony Saputra

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 461-475

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2472522

A Deep Learning–Based Causal Knowledge Extraction Method for Supporting the Development of Nuclear Power Plant Operator Knowledge Base

Pengfei Fu, Licao Dai

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 476-489

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2472526

Investigation of Reactivity Coefficient Characteristics in Actinide Burning Core Concept for the Future Phaseout of a Fast Reactor Fuel Cycle

Tetsuya Mouri, Shigeo Ohki

Nuclear Technology / Volume 212 / Number 2 / February 2026 / Pages 490-509

Regular Research Article / dx.doi.org/10.1080/00295450.2025.2472530