Availability of Critical Benchmark Experiments for the Pebble Tanker Transportation Model for Nuclear Criticality Safety Validation of TRISO Pebbles Journal December, 2024
Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Journal June, 2024
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems... Journal February, 2024
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Journal June, 2023
Horizontal Split-Table Conceptual Design to Support Advanced Reactor Validation Needs Journal January, 2023
Measurement of the Effective Capture Cross Section of 238Np in the High Flux Isotope Reactor Journal June, 2022
Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: 1H, C, 58,60Ni, 182,183,184,186W, 235,238U, 239Pu Journal May, 2022
Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations Journal January, 2022
