Initial Neutronics and Thermal-Hydraulic Coupling for Spent Nuclear Fuel Canister... ORNL Report September, 2019
Coupled Deterministic and Monte Carlo Neutronics for Vessel Fluence Calculations Conference Paper August, 2019
A Method for Performing k?ff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS Conference Paper June, 2019
Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters Conference Paper April, 2019
Dose to Cementitious Material for Moderator Exclusion in a Spent Nuclear Fuel Canister During a Repository Timeframe Conference Paper April, 2019
Dual-purpose canister filling simulation and validation: Part II- Validation Conference Paper April, 2019
Dual-purpose canister filling simulation and validation: Part I - Simulations Conference Paper April, 2019
