ANS / Publications / Journals / Nuclear Science and Engineering

Generational Variance Reduction in Monte Carlo Criticality Simulations as a Way of Mitigating Unwanted Correlations

Kévin Fröhlicher, Eric Dumonteil, Loïc Thulliez, Julien Taforeau, Mariya Brovchenko

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 527-544

Research Article / dx.doi.org/10.1080/00295639.2023.2193089

High-Fidelity Transient Analysis with STREAM Based on the Predictor-Corrector Quasi-Static Method

Anisur Rahman, Hyun Chul Lee, Deokjung Lee

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 545-564

Research Article / dx.doi.org/10.1080/00295639.2023.2194219

Continuous-Energy Time-Dependent Coarse Mesh Transport (COMET) Method for Kinetics Calculations

Dingkang Zhang, Farzad Rahnema

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 565-577

Research Article / dx.doi.org/10.1080/00295639.2023.2196935

Statistical Methods for the Study of Computer Experiment Failures: Application to a Fuel-Coolant-Interaction Simulation Code

Faouzi Hakimi, Claude Brayer, Amandine Marrel, Fabrice Gamboa, Benoît Habert

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 578-591

Research Article / dx.doi.org/10.1080/00295639.2023.2197838

A Novel Hybrid Deterministic and Monte Carlo Neutron Transport Formulation and Algorithm (tRAPID) for Accurate and Fast 3-D Reactor Kinetics

Valerio Mascolino, Alireza Haghighat

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 592-627

Research Article / dx.doi.org/10.1080/00295639.2023.2197844

High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations

Farzad Rahnema, Dingkang Zhang

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 628-639

Research Article / dx.doi.org/10.1080/00295639.2023.2204820

Propagation of Uncertainties due to Nuclear Data for the LCT086 Reactor System

G. P. Nyalunga, V. V. Naicker

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 640-657

Research Article / dx.doi.org/10.1080/00295639.2023.2205198

Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores

Naoto Aizawa, Cheol Ho Pyeon

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 658-672

Research Article / dx.doi.org/10.1080/00295639.2023.2212580

Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety

Jeongwon Seo, Hany S. Abdel-Khalik, Ugur Mertyurek, Goran Arbanas, William Marshall, William Wieselquist

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 673-701

Research Article / dx.doi.org/10.1080/00295639.2023.2211202

Resonance Scattering Treatment with the Windowed Multipole Formalism

Gavin Ridley, Benoit Forget, Timothy Burke

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 702-726

Research Article / dx.doi.org/10.1080/00295639.2023.2204810

Rapid Quenching of Molten Salts as an Approach for the Coordination Characterization of Corrosion Products

Juho Lehmusto, J. Matthew Kurley, III, Ercan Cakmak, James R. Keiser, Daniel Lindberg, Markus Engblom, Bruce A. Pint, Stephen S. Raiman

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 727-734

Research Article / dx.doi.org/10.1080/00295639.2023.2204175

CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model

Samyak S. Munot, Arun K. Nayak

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 735-748

Research Article / dx.doi.org/10.1080/00295639.2023.2197015

A Method for Inhibiting Corrosion of Type 316L Stainless Steel in High-Temperature Molten Chloride Salt

Brendan D’Souza, Amanda Leong, Jinsuo Zhang

Nuclear Science and Engineering / Volume 198 / Number 3 / March 2024 / Pages 749-753

Note / dx.doi.org/10.1080/00295639.2023.2199679