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

Deterministic High-Fidelity Neutronics Simulation of Pebble Bed Reactors Using Pebble Tracking Transport

Liam Carlson, Jean C. Ragusa, Paolo Balestra, Yaqi Wang

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S574-S594

Research Article / dx.doi.org/10.1080/00295639.2025.2471722

Selection of Sampling and Surrogate Modeling Methods for State-Point Evaluations of an AGN-201M Reactor

Quinton J. Williams, Ryan H. Stewart, Todd S. Palmer, Camille J. Palmer, Chad Pope, Ashley Shields, Christopher Ritter

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S391-S405

Research Article / dx.doi.org/10.1080/00295639.2025.2455908

Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System

Michel Saliba, Vincent Lamirand, Wilfried Monange, Fanny Vitullo, Mathieu Hursin, Andreas Pautz, Oskari Pakari

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S406-S414

Research Article / dx.doi.org/10.1080/00295639.2025.2456411

Time-Dependent Variants of The Random Ray Method for Transient Simulations

Maximilian Kraus, Paul Cosgrove, Eugene Shwageraus

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S415-S435

Research Article / dx.doi.org/10.1080/00295639.2025.2456413

Prediction of Exotic (n,2n) Cross Sections Using a Regression Tree Machine Learning Algorithm

Rohan Teelock-Gaya, Valeria Raffuzzi, Eugene Shwageraus, Lee Morgan

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S436-S455

Research Article / dx.doi.org/10.1080/00295639.2025.2456414

An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media

Zhe Chuan Tan, Zhi Yuan Feng, Kan Wang

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S456-S465

Research Article / dx.doi.org/10.1080/00295639.2025.2456895

A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels

Mathis Caprais, André Bergeron, Nathan Greiner, Daniele Tomatis

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S466-S484

Research Article / dx.doi.org/10.1080/00295639.2025.2458345

Application of the Random Ray Method to Variance Reduction in Radiation Shielding Problems

Valeria Raffuzzi, Rufus Neame, Paul Cosgrove

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S485-S502

Research Article / dx.doi.org/10.1080/00295639.2025.2458958

Comparison of Analytical Models for Frequency Response and Linear Stability of Molten Salt Reactors

Lubomír Bureš

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S503-S526

Research Article / dx.doi.org/10.1080/00295639.2025.2460318

Hermes Reactor Demonstration, Initial Startup, and Physics Testing

Nader Satvat, Richard Hernandez, Fanny Vitullo, Kyrone Riley, Massimilliano Fratoni, Brandon Haugh, Edward Blandford

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S527-S537

Research Article / dx.doi.org/10.1080/00295639.2025.2462892

Uncertainty Analysis of the Reaction Rates in Ringhals

Jacob Persson

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S538-S545

Research Article / dx.doi.org/10.1080/00295639.2025.2464452

Coupled Adjoint-Based Perturbation Theory for Dynamics and Heat Transfer Multiphysics for Nuclear Transients

Alexis Maldonado, Christopher M. Perfetti

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S546-S564

Research Article / dx.doi.org/10.1080/00295639.2025.2465220

Neutron Noise Measurements of a Fast HEU Copper System

Cole Kostelac, Robert Weldon, Nicholas Whitman, Nicholas Thompson, Theresa Cutler, Kelsey Amundson, Ayodeji Alajo

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S565-S573

Research Article / dx.doi.org/10.1080/00295639.2025.2471240

A 2-D Physics Study for Understanding Moderator Temperature Coefficient of Burnable Absorber–Loaded Prismatic High-Temperature Helium-Cooled Reactor

Davide Bazzani, S. Wijaya, A. Cammi, Y. Kim

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S378-S390

Research Article / dx.doi.org/10.1080/00295639.2025.2455900

Development of Serpent/CTF External Coupling for the OECD/NEA TVA-WB1 Benchmark Activities

T. Albagami, P. Rouxelin, A. Abarca, S. Palmtag, M. Avramova, K. Ivanov

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S595-S610

Research Article / dx.doi.org/10.1080/00295639.2025.2475415

Material Composition Interpolation for High-Assay Low-Enriched Uranium Fuel Macroscopic Cross-Section Estimation Using Gaussian Process

Junsu Kang, Andrew M. Ward, Ugur Mertyurek, Thomas J. Downar

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S611-S624

Research Article / dx.doi.org/10.1080/00295639.2025.2494184

Parallel Simulated Annealing, Genetic Algorithms, and Hybrid Method Applied to the Multiobjective Optimization of the Nuclear In-Core Fuel Management

Wojciech Kubinski, Gianluca Giorgi, Mathieu Segond

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S625-S643

Research Article / dx.doi.org/10.1080/00295639.2025.2495520

Multiphysics Running-In Simulations for Pebble-Bed Reactors with Griffin

Joshua Hanophy, Paolo Balestra, Yaqi Wang, Javier Ortensi, Sebastian Schunert

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S644-S658

Research Article / dx.doi.org/10.1080/00295639.2025.2497025

Quantification and Propagation of Uncertainties in R-Matrix Limited Resonance Parameters

Pierre Sole, Vaibhav Jaiswal, Cédric Jouanne

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S659-S675

Research Article / dx.doi.org/10.1080/00295639.2025.2508040

Reactor Physics Modeling Challenges for the FLEX Reactor

Simon Boddington, Tom Taylor, Peter Haigh, Eduardo Cuoc, Chris Hankinson, Luke Godfrey

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S676-S692

Research Article / dx.doi.org/10.1080/00295639.2025.2524266

First Steps of the ANTARES Validation for Steady States with TVA Watts Bar Unit 1 Cycle 1 Benchmark

Franck Bernard, Sébastien Bonthoux, Marc Forestier, Antonio Sargeni, Julien Taforeau

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S693-S706

Research Article / dx.doi.org/10.1080/00295639.2025.2530299

An Optimization Approach to Improve Thermal Scattering Law Using Experimental Total Cross-Section Data

Vaibhav Jaiswal, Pierre Sole

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S707-S726

Research Article / dx.doi.org/10.1080/00295639.2025.2530301

Assessing the Impact of Improved Thermal Conductivity of UO₂-Mo Fuel Using the ENIGMA Fuel Performance Code

Aiden Peakman, Glyn Rossiter

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S727-S740

Research Article / dx.doi.org/10.1080/00295639.2025.2541338

First Results for Uranium Nitride Fuel Characterization Using an Accelerated Fuel Qualification Process

Zachary Miller, Landon Johnson, Lorena Alzate-Vargas, Jason Rizk, Christopher Matthews, Michael W. D. Cooper, Vedant Mehta, David A. Andersson, Galen T. Craven, Massimiliano Fratoni, Alex Levinsky

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S741-S753

Research Article / dx.doi.org/10.1080/00295639.2025.2567814

Development of New GPU-Optimized Reactor Physics Monte Carlo Code GREAPMC

Muhammad Rizwan Ali, Murat Serdar Aygul, Deokjung Lee

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S754-S769

Note / dx.doi.org/10.1080/00295639.2025.2502714

Stochastic Optimization to Find Optimum Beginning-of-Life Core Configuration of Stable Salt Reactor with Online Refueling

Seungug Jae, Won Sik Yang, Thanh Hua, Yan Cao, Tom Taylor, Luke Godfrey

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S198-S211

Research Article / dx.doi.org/10.1080/00295639.2024.2423131

Study of the Phenomena Affecting the Efficiency of the Fission Gas Removal System in the Fuel Circuit of a Molten Salt Reactor

M. Marone, P. Rubiolo, N. Capellan, J. Giraud

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S15-S38

Review Article / dx.doi.org/10.1080/00295639.2025.2455884

Squirrel: A MOOSE-Based App for Solving Point Kinetics in Molten Salt Reactors

P. Pfahl, A. Chambon, J. Groth-Jensen, B. Lauritzen

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S39-S51

Review Article / dx.doi.org/10.1080/00295639.2025.2494182

Impact of the Multigroup Velocity Approximation in the Evaluation of the Effective Neutron Lifetime

Giorgio Valocchi, Elias-Yammir Garcia-Cervantes, Laurent Buiron, Jean Tommasi

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S52-S62

Review Article / dx.doi.org/10.1080/00295639.2025.2515348

Real-Time State Estimation of Neutron Flux in Molten Salt Fast Reactors from Out-Core Sparse Measurements

Stefano Riva, Sophie Deanesi, Carolina Introini, Stefano Lorenzi, Antonio Cammi

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S63-S76

Review Article / dx.doi.org/10.1080/00295639.2025.2531477

A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method

Alain Hébert

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S77-S90

Research Article / dx.doi.org/10.1080/00295639.2024.2375908

Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation

Akio Yamamoto, Tomohiro Endo, Satoshi Takeda, Kazuya Yamaji, Hiroki Koike, Koji Asano

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S91-S104

Research Article / dx.doi.org/10.1080/00295639.2024.2384236

Linear Sources and Anisotropic Scattering in the Random Ray Method

Rufus Neame, Paul Cosgrove

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S105-S121

Research Article / dx.doi.org/10.1080/00295639.2024.2394729

Optimized Dropping and Rolling and Virtual Surface Method for High Packing Fraction of Dispersed Fuel Particles in Annular Container

Zhiyuan Feng, Jingang Liang, Wenli Guo, Kan Wang

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S122-S130

Research Article / dx.doi.org/10.1080/00295639.2024.2403896

Reactivity Impact of Updated ³⁵Cl Nuclear Data on the Molten Chloride Reactor Experiment

T. Cisneros, M. Wargon, B. Harper, K. Hanselman, T. Kawano, S. A. Kuvin, H. Y. Lee

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S131-S141

Research Article / dx.doi.org/10.1080/00295639.2024.2413787

Verification and Validation of the VANGARD Pinwise Nodal Code with Analyses of BEAVRS

Seoyoon Jeon, Brendan Kochunas

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S142-S165

Research Article / dx.doi.org/10.1080/00295639.2024.2421095

Improving the Resolution and Computational Efficiency of Depletion Simulations on a TRISO-Fueled Microreactor

Keenan J. Hoffman, Alexis Maldonado, Todd S. Palmer

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S166-S179

Research Article / dx.doi.org/10.1080/00295639.2024.2423124

Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor

Puran Deng, Won Sik Yang, Thomas Wielenga

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S180-S197

Research Article / dx.doi.org/10.1080/00295639.2024.2423129

Resonance Treatment of Double-Heterogeneous Fuel Using a Deterministic Statistical Geometry Method in Heterogeneous Transport Calculation Code GALAXY-Z

Kazuya Yamaji, Hiroki Koike, Koji Asano, Satoshi Takeda, Akio Yamamoto

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S1-S14

Review Article / dx.doi.org/10.1080/00295639.2024.2397259

Dynamics of Molten Salt Reactor with Operating Heaters

Thabit Abuqudaira, Pavel Tsvetkov, Piyush Sabharwall

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S212-S233

Research Article / dx.doi.org/10.1080/00295639.2024.2423132

Analytical Description of the Neutron Up-Scattering in the Resonance Range

A. Bengoechea, G. Noguere, D. Bernard, P. Tamagno

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S234-S244

Research Article / dx.doi.org/10.1080/00295639.2024.2439676

Welch Method and Bootstrapping Applied to Subcritical Gamma Noise

Flynn B. Darby, Schuyler J. Tyler, Oskari V. Pakari, Vincent P. Lamirand, Shaun D. Clarke, Andreas Pautz, Sara A. Pozzi

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S245-S252

Research Article / dx.doi.org/10.1080/00295639.2024.2445469

Temperature Prediction for the Sirius-2c Nuclear Propulsion Fuel Experiment Conducted at the TREAT Facility

Mustafa K. Jaradat, Sebastian Schunert, Frederick N. Gleicher, Mark DeHart

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S253-S269

Research Article / dx.doi.org/10.1080/00295639.2024.2445470

First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling

B. D. Ganapol, J. K. Patel

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S270-S282

Research Article / dx.doi.org/10.1080/00295639.2024.2445987

A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors

Nicolò Abrate, Alex Aimetta, Mattia Massone, Sandra Dulla, Piero Ravetto

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S283-S308

Research Article / dx.doi.org/10.1080/00295639.2024.2446130

Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning

Majdi I. Radaideh, Leo Tunkle, Dean Price, Kamal Abdulraheem, Linyu Lin, Moutaz Elias

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S309-S321

Research Article / dx.doi.org/10.1080/00295639.2024.2447012

Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration

S. Lapaire, T. Bonaccorsi, J-M. Palau

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S322-S331

Research Article / dx.doi.org/10.1080/00295639.2025.2453787

Comparison of ²³⁸U and ²³⁵U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accelerator-Driven Subcritical Reactor Using the Current-to-Flux Method

Nathalie Marie, Annick Billebaud, Sébastien Chabod, Anatoly Kochetkov, Antonin Krása, François-René Lecolley, Jean-Luc Lecouey, Grégory Lehaut, Nadia Messaoudi, Guido Vittiglio, Jan Wagemans

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S332-S341

Research Article / dx.doi.org/10.1080/00295639.2025.2453789

A Novel ERANOS Procedure for Sensitivity Analyses in Core Depletion Problems: Implementation Details and Verification

Matteo Stanzani, Donato M. Castelluccio, Francesco Lodi, Vincenzo G. Peluso, Giacomo Grasso, Marco Sumini

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S342-S365

Research Article / dx.doi.org/10.1080/00295639.2025.2455341

Assessment of the Influence of Secondary Sources on the Thermal-Hydraulic Behavior of FRM II Using Serpent 2 and Ansys CFX

Kaltrina Shehu, Daniel Bonete Wiese, Christian Reiter

Nuclear Science and Engineering / Volume 200 / Number 1S / March 2026 / Pages S366-S377

Research Article / dx.doi.org/10.1080/00295639.2025.2455348

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

Benchmark-Quality Results for Transport Problems Involving a Void Region in Spherical Geometry

R. D. M. Garcia

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 753-765

Research Article / dx.doi.org/10.1080/00295639.2025.2471695

Double PN Benchmark for the One-Dimensional Plane Geometry Monoenergetic Neutron Transport Equation with Anisotropic Scatter

B. D. Ganapol, D. Mostacci

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 766-780

Research Article / dx.doi.org/10.1080/00295639.2024.2423130

Analytic Solutions for Strong Blast Wave Radiographs

William Bennett, Ryan G. McClarren, Jim Ferguson

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 781-799

Research Article / dx.doi.org/10.1080/00295639.2025.2584756

Tensor Train Neutron Transport Applied to Nuclear Reactor Problems

Mario I. Ortega, Duc P. Truong, Ismael Boureima, Kim Ø. Rasmussen, Boian S. Alexandrov

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 800-820

Research Article / dx.doi.org/10.1080/00295639.2025.2505804

An Analytical Discrete Ordinates Solution for the Two-Dimensional Transport Equation with Exact Representation of the Scattering Law

Liliane Basso Barichello, Rudnei Dias da Cunha, Maiara Mentges

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 821-846

Research Article / dx.doi.org/10.1080/00295639.2025.2602120

Neutron Counting Statistics Calculations Using Deterministic Transport

Philippe Humbert

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 847-864

Research Article / dx.doi.org/10.1080/00295639.2025.2480520

High-Order Stochastic Perturbation Method for Updating Response Functions for Changes in Material Density and Isotopic Atom Density

Farzad Rahnema, Dingkang Zhang

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 865-876

Research Article / dx.doi.org/10.1080/00295639.2025.2460389

Second Phases in Zr Alloys: A Review

Muhammad Ali, Fuzhou Han

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 877-903

Regular Review Article / dx.doi.org/10.1080/00295639.2025.2502887

A Review on Plastic Scintillator Development and Performance for Gamma-Ray Detection

Rizka Fitriana, Yeni Febrianti, Rahmawati Rahmawati, Adhi Harmoko Saputro

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 904-931

Regular Review Article / dx.doi.org/10.1080/00295639.2025.2503030

Reliability Assessment of Passive Nuclear Systems Influenced by Corrosion in Stratified Hot Fluids

Akmali Masood, Robert Plana

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 932-942

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2502889

Analysis of Zero-Variance Schemes for Radiation Shielding Problems Including Neutron Multiplication

Thayz Gomes Ferreira, Alexis Jinaphanh, Davide Mancusi, Andrea Zoia

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 943-975

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2496859

Demonstration of TOFFEE: A Response Uncertainty Quantification Tool

Austin Williams, Lance Drouet, Sandra Bogetic

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 976-990

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2500259

Scoping Analysis of Pebble-Bed Reactors for the Destruction of the Transuranic Inventory of LWR Spent Nuclear Fuel

Annie Berens, Friederike Bostelmann, Nicholas R. Brown

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 991-1011

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2497094

SAINT: A Computational Framework for Time-Dependent Neutron Transport

Peter Schwanke, Eleodor Nichita

Nuclear Science and Engineering / Volume 200 / Number 4 / April 2026 / Pages 1012-1046

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2497024