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
