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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
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!
Latest Magazine Issues
Dec 2025
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Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
What’s the most difficult question you’ve been asked as a maintenance instructor?
Blye Widmar
"Where are the prints?!"
This was the final question in an onslaught of verbal feedback, comments, and critiques I received from my students back in 2019. I had two years of instructor experience and was teaching a class that had been meticulously rehearsed in preparation for an accreditation visit. I knew the training material well and transferred that knowledge effectively enough for all the students to pass the class. As we wrapped up, I asked the students how they felt about my first big system-level class, and they did not hold back.
“Why was the exam from memory when we don’t work from memory in the plant?” “Why didn’t we refer to the vendor documents?” “Why didn’t we practice more on the mock-up?” And so on.
Jump to:
An Evaluation and Qualification of U.S.-Based Research Reactors for Irradiation Capabilities Supporting Advanced Nuclear Systems
Palash K. Bhowmik, Richard H. Howard, Braden Clayton, Piyush Sabharwall, Susan Hogle, Allen Roach, Joseph W. Nielsen, Misti Lillo, Bryce D. Kelly, Brenden Heidrich, Andrew Zillmer
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 1-17
Review Article | doi.org/10.1080/00295639.2025.2512258
Accelerated Irradiation Testing and Post-Irradiation Characterization: U.S.-Based Capabilities for Advanced Nuclear Systems and Radioisotope Production
Palash K. Bhowmik, Changhu Xing, Richard Skifton, Piyush Sabharwall, Brenden Heidrich, Susan Hogle, Allen Roach, Andrew Zillmer, Richard H. Howard, Joseph W. Nielsen, Bryce D. Kelly
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 18-38
Review Article | doi.org/10.1080/00295639.2025.2550913
Conceptual Design of a Thermal–to–14-MeV Neutron Conversion Device for Use in the Advanced Test Reactor
Nicolas P. Martin, Andrew J. Bascom, Jason V. Brookman, Nicolas E. Woolstenhulme
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 39-57
Research Article | doi.org/10.1080/00295639.2024.2387967
Contribution of Lobe Power to Experiment Heating in the Advanced Test Reactor
Michael J. Worrall, Joseph W. Nielsen
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 58-68
Research Article | doi.org/10.1080/00295639.2024.2397623
Thermal Model of the AGR-5/6/7 Experiment with Offset Gas Gaps
Grant Hawkes, Binh Pham, Courtney Otani
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 69-94
Research Article | doi.org/10.1080/00295639.2024.2368994
Cross-Code Verification of Neutronics Analysis Tools at INL Applied for 238Pu Production in the Advanced Test Reactor
Brittany Grayson, Jill Mitchell
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 95-104
Research Article | doi.org/10.1080/00295639.2024.2444133
Projection Analysis for ATR Irradiation of the AFC-FAST Experiment
Andrew J. Bascom
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 105-111
Research Article | doi.org/10.1080/00295639.2025.2456365
Evaluation of U10Mo Fuel Plate Performance Modeling Over Hot Isostatic Press and Hydraulic Bending for MURR DDE Plates
Kyle M. Paaren, Jason Schulthess, Jason Barney, Hakan Ozaltun
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 112-122
Research Article | doi.org/10.1080/00295639.2025.2545155
Interaction of Polymethyl Methacrylate with Boehmite-Filmed Aluminum Cladding Under Gamma Irradiation
Daniel K. Sluder, Bryon J. Curnutt, Lorenzo Vega-Montoto, Joshua D. Orchard, Matthew D. Horkley, Trevor J. Skeen, Dean A. Stewart
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 123-135
Research Article | doi.org/10.1080/00295639.2024.2406714
Impact of High-Reactivity Advanced Test Reactor Experiments on Photon Heating in Nearby Experiment Locations
Paul E. Gilbreath, Michael J. Worrall, Joseph W. Nielsen, Greg K. Housley
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 136-147
Research Article | doi.org/10.1080/00295639.2024.2415813
The LYRA-10 Experiment: Irradiation of Light Water Reactor Pressure Vessel Steels with Systematic Variations in Ni, Mn, and Si Contents to Assess Long-Term Operation–Enhanced Embrittlement
E. D’Agata, B. Acosta Iborra, A. J. Magielsen, M. Kolluri, O. Martin, C. Sciolla, R. A. F. Okel, B. T. Straathof
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 148-164
Research Article | doi.org/10.1080/00295639.2024.2437938
Neutronic Design of the Centrifugal Nuclear Thermal Rocket
Zuolong Zhu, Dean Wang
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 165-180
Regular Research Article | doi.org/10.1080/00295639.2025.2480944
Nondestructive Measurement Method of Nuclear Materials for Sorting Nuclear Fuel Debris
Makoto Maeda, Masao Komeda, Yosuke Toh
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 181-194
Regular Research Article | doi.org/10.1080/00295639.2025.2480516
An Automatic Load-Balancing Domain Decomposition Scheme for Monte Carlo Simulation on Large-Scale Unstructured-Mesh Problems
Hanlin Shu, Liangzhi Cao, Qingming He, Tao Dai
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 195-221
Regular Research Article | doi.org/10.1080/00295639.2025.2480517
An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents
Peiqi Huang, Liang Chen, Meng Xia, Guogang Bao, Haopeng Chen
Nuclear Science and Engineering | Volume 200 | Number 1 | January 2026 | Pages 222-239
Regular Research Article | doi.org/10.1080/00295639.2025.2480509
