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Volume 200

Number 1

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.1080/00295639.2025.2480509