Development of Terrenus, a Multiphysics Code for Spent Nuclear Fuel Cask Criticality Analysis Conference Paper September, 2019
Initial Neutronics and Thermal-Hydraulic Coupling for Spent Nuclear Fuel Canister... ORNL Report September, 2019
Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy... Journal September, 2019
NCSP Analytical Methods Subtask 3 & NCSP Nuclear Data Subtask 6: AMPX Development and Maintenance & SAMMY Modernization ORNL Report September, 2019
Coupled Deterministic and Monte Carlo Neutronics for Vessel Fluence Calculations Conference Paper August, 2019
Activation Study of Isotopically Enriched Samples During Neutron TOF Measurements ORNL Report August, 2019
Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-Group Libraries for Advanced Reactor Analysis... Conference Paper August, 2019
