AMPX: A Modern Cross Section Processing System for Generating Nuclear Data Libraries Conference Paper September, 2015
Development and Testing of Neutron Cross Section Covariance Data for SCALE 6.2... Conference Paper September, 2015
VALIDATION STUDY FOR CREDITING CHLORINE IN CRITICALITY ANALYSES FOR SPENT NUCLEAR FUEL DISPOSITION Conference Paper September, 2015
Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark3 BWR Spent Fuel... Conference Paper September, 2015
Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems... Conference Paper September, 2015
Analysis of Axial Coolant Density Profile, Control Blade History, and Axial Burnup Profile on Extended Burnup Credit Conference Paper August, 2015
Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS... Conference Paper August, 2015
