Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geom... Journal September, 2013
Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor... Journal September, 2013
A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA... Journal September, 2013
AGR-1 Irradiated Compact 4-4-2 PIE Report: Evaluation of As-Irradiated Fuel Performance with Leach Burn Leach, IMGA, Materialography, and X-ray Tomography ORNL Report September, 2013
Reversible Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation... Conference Paper August, 2013
Material Selection for Fuel Cladding Resistant to Severe Accident Scenarios... Conference Paper August, 2013
Consequence Analysis of Spent Nuclear Fuel Reconfiguration Scenarios... Conference Paper August, 2013