SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems... Journal February, 2024
A Review of Candidates for a Validation Data Set for High-Assay Low-Enrichment Uranium Fuels Journal August, 2023
Editorial: Benchmark experiments, development and needs in support of advanced reactor design Journal July, 2023
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Journal June, 2023
High Flux Isotope Reactor Neutron Spectrum Shape Estimation From Activation Experiment Data Journal January, 2023
Code Verification and Solution Verification framework in pin-resolved neutron transport code MPACT... Journal December, 2022
PCM-based uncertainty reduction in support of model validation for depletion calculations Journal December, 2022
Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor... Journal August, 2022
