ANS / Publications / Journals / Nuclear Science and Engineering

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

On MCNP Stochastic Volume Estimation Normalization

Joel A. Kulesza

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 241-245

Research Article / dx.doi.org/10.1080/00295639.2025.2483123

SCALE Shielding Calculations for Advanced Reactor Accident Scenarios

Georgeta Radulescu, Donny Hartanto, Friederike Bostelmann, William A. Wieselquist

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 246-256

Research Article / dx.doi.org/10.1080/00295639.2025.2503125

Toward Efficient Nuclear Data Uncertainty Quantification in Radiation Shielding Calculations

Juan A. Monleon de la Lluvia, Mariya Brovchenko, Dimitri Rochman, Eric Dumonteil

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 257-279

Research Article / dx.doi.org/10.1080/00295639.2025.2510048

Shielding Material Performance in a Preconcept Spherical Tokamak Power Plant

Kamya Chandrasekhar, Alexander Lin-Vines, Christopher Wilson, Gurdeep Singh Kamal, Mayank Rajput

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 280-292

Research Article / dx.doi.org/10.1080/00295639.2025.2548107

Methodologies and Shielding Analysis for the Design of Activated Cooling Water Components in Spallation Neutron Systems

Ahmad M. Ibrahim, Franz X. Gallmeier, Tucker C. McClanahan, Don Montierth, Igor Remec, Irina I. Popova

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 293-311

Research Article / dx.doi.org/10.1080/00295639.2025.2545733

Advancing the MCNP Unstructured Mesh Calculations at ORNL’s Second Target Station with Attila4MC-Cottonwood^TM

Lukas Zavorka, Igor Remec, Andrew Cooper, Jonathan Rogers, Gregory Failla

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 312-319

Research Article / dx.doi.org/10.1080/00295639.2025.2551385

Analysis of Second Target Station Target Removal Dose Rates

Tucker C. McClanahan, Igor Remec

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 320-334

Research Article / dx.doi.org/10.1080/00295639.2025.2515656

Optimal Additive Dose Distributions for Minimizing Dose Estimate Error in Retrospective and Emergency Dosimetry with Heteroscedastic Effects

Melody G. Polk, Robert B. Hayes

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 335-347

Research Article / dx.doi.org/10.1080/00295639.2025.2480858

Study on Fission Decay Width of Superheavy Nuclei ²⁹⁸119 Synthesized Through the Various Fusion Reactions

N. Manjunatha, H. C. Manjunatha, N. Sowmya, T. Ganesh, T. Nandi

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 348-356

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2483595

Nonequilibrium Thermodynamic Analysis of High-Energy Neutron Scattering

Takashi Hirai, Shin Nakatani, Motoyasu Sato

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 357-365

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2486899

Image Style Transfer–Based High- and Low-Frequency Component Synthesis Neural Architecture for Low-Dose Computed Tomography Denoising

Shan Liao, Li Yang, Yanghui Wang, Sangang Li, Yi Cheng

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 366-382

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2483120

Accelerating Long-Term Xenon Dynamics Prediction: A Reduced-Order Hybrid Recurrent Neural Network with Intrinsic Physics

Helin Gong, Qing Li

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 383-403

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2487382

Development of Multiphysics Tests for Verification of Dry Storage Cask Content via the BERRU Framework

Zi Liang Tan, Eugene Shwageraus

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 404-428

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2483081

Statistical Study of Stress and Strain in Matrix of UO₂-Zr Plate Type Fuel

S. Mirzaee, M. Aghaie

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 429-443

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2484878

Automated Hybrid Variance Reduction on Advanced Architectures in the Shift Monte Carlo Code

Thomas M. Evans, Katherine E. Royston, Steven P. Hamilton, Gregory G. Davidson, Elliott Biondo, Seth R. Johnson

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 444-470

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2484511

Validation and Verification of Serpent-Griffin Computational Sequence Using the SNAP 8 Experimental Reactor Dry Experiments

Isaac Naupa, Samuel Garcia, Ben Lindley, Stefano Terlizzi, Dan Kotlyar

Nuclear Science and Engineering / Volume 200 / Number 2 / February 2026 / Pages 471-487

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2483071

An Analytic Benchmark for Neutron Boltzmann Transport with Downscattering—Part IV: PFNS and $\overline{ν}$ Uncertainty Propagation

A. M. Lewis, V. Sobes, D. Neudecker, N. Gibson, W. Fritsch

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 489-501

Research Article / dx.doi.org/10.1080/00295639.2025.2489769

Collision-Based Hybrid Method for Two-Dimensional Neutron Transport Problems

Ben Whewell, Ryan G. McClarren

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 502-524

Research Article / dx.doi.org/10.1080/00295639.2025.2489778

A Residual Monte Carlo Algorithm for Continuous Energy Neutron Transport with Elastic Scattering

Massimo A. Larsen, Simon Bolding, Todd Palmer, Jim Morel

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 525-538

Research Article / dx.doi.org/10.1080/00295639.2025.2495608

A Novel Physics-Constrained Dynamic Mode Decomposition–Based Neutronics-Depletion Coupling Method for Efficient Burnup Calculation in Nuclear Reactors

Binhang Zhang, Hanyuan Gong, Yonghong Zhang, Xianbao Yuan, Haibo Tang

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 539-561

Research Article / dx.doi.org/10.1080/00295639.2025.2490312

Use of Constrained Gamma Emission Computed Tomography to Evaluate Fission Product Distributions in High-Temperature Materials from a TRISO Fuel Irradiation

Adriaan A. Riet, John D. Stempien

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 562-573

Research Article / dx.doi.org/10.1080/00295639.2025.2489253

Surpassing Legacy Approaches to PWR Core Reload Optimization with Single-Objective Reinforcement Learning

Paul Seurin, Koroush Shirvan

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 574-605

Research Article / dx.doi.org/10.1080/00295639.2025.2488702

Expanded Accident Scenarios and Frequency Characteristics for a Fast Spectrum Molten Salt Reactor in an Integrated Energy System

Nicholas Dunkle, Sandra Bogetic, Nicholas R. Brown

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 606-619

Research Article / dx.doi.org/10.1080/00295639.2025.2489172

Effects of Temperature and Electron Energy on the Defect Evolution Behavior of Pristine and Ion-Irradiated Yttria-Stabilized Zirconia

AKM Saiful Islam Bhuian, Tomokazu Yamamoto, Hidehiro Yasuda, Norito Ishikawa, Kazuhiro Yasuda

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 620-631

Research Article / dx.doi.org/10.1080/00295639.2025.2494185

Sensitivity Analysis of an Overcooling Transient in the Generic Fluoride-Salt-Cooled High-Temperature Reactor

Jonathan L. Barthle, Isabelle O. Lindsay, Nader Satvat, Nicholas R. Brown

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 632-652

Research Article / dx.doi.org/10.1080/00295639.2025.2494290

Identification of Important Phenomena for Light Water Reactors During Heat Transport System Failure Events in Integrated Energy Systems

Emily V. Meilus, Isabelle O. Lindsay, Jamie B. Coble, Nicholas R. Brown

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 653-663

Research Article / dx.doi.org/10.1080/00295639.2025.2495610

Three-Dimensional Experimental Validation of an EGSnrc Monte Carlo Model for the Elekta Synergy MLCi2 Linear Accelerator

Yassir El Ghazi, Samir Didi, Karim Bahhous, Dikra Bakari, Abdeslem Rrhioua, Mustapha Zerfaoui

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 664-678

Research Article / dx.doi.org/10.1080/00295639.2025.2494188

Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN

Nikolai Vododokhov, David R. Novog

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 679-695

Research Article / dx.doi.org/10.1080/00295639.2025.2494187

Assessment of TN-24 Cask Loaded with VVER-1200 Spent Fuel Assemblies from the Radiological Regulatory Limits

Amr Abdelhady, Rowayda Fayez M. AbouAlo, Mohamed K. Shaat

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 696-706

Research Article / dx.doi.org/10.1080/00295639.2025.2494186

Salt Composition Selection for Molten Salt Reactors: Required Pumping Power, Heat Exchanger Size, and Other Considerations

Elliott J. T. Berg, Adriaan Buijs

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 707-722

Research Article / dx.doi.org/10.1080/00295639.2025.2489882

Validation of the AGREE HTR Analysis Code with the HTR-PROTEUS Experiments

Sefa Bektas, Volkan Seker, Thomas Downar, Uner Colak, Köberl Oliver, John D. Bess

Nuclear Science and Engineering / Volume 200 / Number 3 / March 2026 / Pages 723-751

Research Article / dx.doi.org/10.1080/00295639.2025.2494189