Photon detector response function methodology using MCNP and shift hybrid radiation transport code for wide-area contamination assay applications Journal March, 2022
Implementation of Two-Phase Gas Transport into VERA for Molten Salt Reactor Analysis Journal January, 2022
Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties Journal January, 2022
Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations Journal January, 2022
Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation Journal December, 2021
