Safety Analysis Models for the Irradiation of 237Np Targets at the High Flux Isotope Reactor... Conference Paper February, 2015
Neutronics Simulations of 237Np Targets to Support Safety-Basis and 238Pu Production Assessment Efforts at the High Flux Isot... Conference Paper February, 2015
Extended Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems Conference Paper January, 2015
Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors... Journal January, 2015
Investigation of inconsistent ENDF/B-VII.1 independent and cumulative fission product yields with proposed revisions... Conference Paper January, 2015
Advancing Inverse Sensitivity/Uncertainty Methods for Nuclear Fuel Cycle Applications... Conference Paper January, 2015
Covariance Applications in Criticality Safety, Light Water Reactor Analysis, and Spent Fuel Characterization... Journal January, 2015
