Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr Journal November, 2024
SCALE depletion capabilities for molten salt reactors and other liquid-fueled systems... Journal February, 2024
Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with Metamodel-Driven Modeling Journal February, 2023
High Flux Isotope Reactor Neutron Spectrum Shape Estimation From Activation Experiment Data Journal January, 2023
CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pre... Journal October, 2022
Assessment of SCALE and MELCOR for a generic pebble bed fluoride high-temperature reactor... Journal August, 2022
Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations Journal January, 2022
