ANS / Publications / Journals / Nuclear Science and Engineering

Assessment of JEFF Nuclear Data Libraries for Reactor Physics and Spent Fuel Composition Applications

Mathieu Hursin, Fan Xia, Dimitri Rochman

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 1987-2000

Research Article / dx.doi.org/10.1080/00295639.2025.2508560

Case Study on the Performance of Bayesian and Frequentist Statistical Approaches for Criticality Safety Evaluations with Used Nuclear Fuel

Alexander Vasiliev, Matthias Frankl, Dimitri Rochman, Hakim Ferroukhi

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2001-2017

Research Article / dx.doi.org/10.1080/00295639.2025.2525033

Methodology for Sample Size Reduction in Uncertainty Analysis with High-Fidelity Fuel Performance Tools

Alejandra de Lara, Zsolt Soti, Arndt Schubert, Paul van Uffelen, Eugene Shwageraus

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2018-2036

Research Article / dx.doi.org/10.1080/00295639.2025.2525035

Impact of Irradiation History on Boltzmann/Bateman Coupled Sensitivities: Application to Sodium-Cooled Fast Reactor Subassembly

Victor Viallon, Elias Y. Garcia Cervantes, Laurent Buiron

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2037-2054

Research Article / dx.doi.org/10.1080/00295639.2025.2534304

Development of a Statistical Model of Uncertainty in Time-Dependent Channel Power Distribution Predictions

J. Rogers, Y. Parlatan

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2055-2065

Research Article / dx.doi.org/10.1080/00295639.2025.2462895

Decay Heat Power Uncertainty Quantification in Studsvik’s System for Spent Fuel Analyses

Teodosi Simeonov, Charles Wemple, Joshua Hykes

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2066-2072

Research Article / dx.doi.org/10.1080/00295639.2025.2455347

Derivation of Uncertainty Distributions for Channel Flow Rate and Fuel Critical Heat Flux Predictions for Best-Estimate Plus Uncertainty Analysis of Slow Loss-of–Reactor Power Regulation Accidents in CANDU Stations

Y. Parlatan, J. Rogers, M. Koivisto

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2073-2082

Research Article / dx.doi.org/10.1080/00295639.2024.2411175

Uncertainty Quantification Framework for High-Temperature Gas-Cooled Reactors Using VSOP and DAKOTA

Gregory K. Delipei, Muhammad Altahhan, Pascal Rouxelin, Sonat Sen, Nathan George, Maria Avramova, Kostadin Ivanov

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2083-2109

Research Article / dx.doi.org/10.1080/00295639.2025.2486901

Multi-Physics Simulations and Sensitivity Analysis of a Main Steam Line Break Transient in a Pressurized Water Reactor

Thomas Croisette, Paolo Olita, Claire Vaglio-Gaudard, Pablo Rubiolo, Raphaël Préa

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2110-2128

Research Article / dx.doi.org/10.1080/00295639.2025.2502888

Bayesian Calibration and Sensitivity Analysis of Rayleigh Scattering Fiber Optic Distributed Temperature Sensing in Water Flow Loop

Lauren Kohler, Darius Lisowski, Matthew Weathered, Xu Wu, Alexander Heifetz

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2129-2142

Research Article / dx.doi.org/10.1080/00295639.2025.2528506

A Reactor Transient Benchmark for Molten Salt Reactor Experiment Pump Transient Tests

Mohamed Elhareef, Youssef Abouhussien, Zeyun Wu, Massimiliano Fratoni, Eva Davidson, Tingzhou Fei, Kurt Harris

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2143-2171

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2475650

Advanced Modeling of the Core of a Prismatic Block Gas-Cooled Reactor

K. Podila, Q. Chen, P. Pfeiffer, X. Huang, S. Golesorkhi, A. Trottier, A. John, S. Kelly

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2172-2192

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2475621

Daily Load-Follow Operation in APR1400 Without Soluble Boron Adjustment Using the Mode-K+

Husam Khalefih, Yunseok Jeong, Yonghee Kim

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2193-2213

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2475414

Computational Investigation of Optimal Discharge Header Design in a Typical Open Pool–Type Research Reactor for Flow Stability in Hot Water Layer System

Haris Iqbal, Muhammad Nadeem, Arif Arif, Adnan Hamid

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2214-2233

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2475640

Ceramic Composite Inert Matrix Fuel Forms in High-Temperature Gas-Cooled Microreactors

Donald L. Doyle, Edward M. Duchnowski, Jason R. Trelewicz, Nicholas R. Brown

Nuclear Science and Engineering / Volume 199 / Number 12 / December 2025 / Pages 2234-2253

Regular Research Article / dx.doi.org/10.1080/00295639.2025.2475645