A Burnup Credit Approach for Margin Estimation of Loaded Boiling Water Reactor Canisters in UNF-ST&DARDS Conference Paper September, 2017
Small-Scale Fuel Irradiation Testing in the High Flux Isotope Reactor Conference Paper September, 2017
Effect of Clad Fast Neutron Flux Distribution on Quarter-Core Fuel Performance Calculations with BISON Conference Paper September, 2017
Fuel Cycle Analysis of Thermal and Fast Spectrum Molten Salt Reactors... Conference Paper September, 2017
A Lumped Parameter MOC Approach and Multigroup Kernels Applied to the Subgroup Self-Shielding Calculation in MPACT Journal September, 2017
Early applications of the R -matrix SAMMY code for charged-particle induced reactions and related covariances... Conference Paper September, 2017
As-Loaded Criticality Margin Assessment of Dual Purpose Canisters Using UNF-ST&DARDS Journal September, 2017