A Misload Analysis Methodology Supporting Criticality Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations Conference Paper September, 2019
Criticality Safety Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations Conference Paper September, 2019
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
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
Dual-purpose canister filling simulation and validation: Part I - Simulations... Conference Paper April, 2019
Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters Conference Paper April, 2019