Validation of UNF-ST&DARDS As-loaded safety analysis methods for BWR decay heat calculations Journal January, 2022
Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3 Journal November, 2021
Reactor Cell Neutron Dose for the Molten Salt Breeder Reactor Conceptual Design... Journal November, 2021
Progress on the reevaluation and validation of the n+ 233 U neutron cross sections... Journal August, 2021
Application of Markov Chain Monte Carlo Methods for Uncertainty Quantification in Inverse Transport Problems... Journal August, 2021
Thermal neutron scattering measurements and modeling of yttrium-hydrides for high temperature moderator applications Journal July, 2021
An Analytic Bookmark for Neutron Boltzmann Transport with Downscattering I. Flux & eigenvalue solutions Journal March, 2021