Development of Terrenus: A Multiphysics Code for Spent Nuclear Fuel Canister Criticality Analysis... Conference Paper November, 2019
Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor Conference Paper November, 2019
Initial Development of a TH Model for Disposal of 37 PWR Dual-Purpose Canisters in Alluvium Conference Paper November, 2019
Monte Carlo Uncertainty Quantification in UF6 Cylinder Neutron Emissions... Conference Paper November, 2019
Dual Purpose Canister Heating Evaluation for Casting of High Temperature Fillers Conference Paper November, 2019
Summary: Verification of the ENDF/B-VII.1 and VIII.0 AMPX 1597-group Libraries for Advanced Reactor Analysis Conference Paper September, 2019
Development of Molten Salt Reactor Modeling and Simulation Capabilities in VERA... Conference Paper September, 2019
Thermal and Neutronic Analysis for Irradiation of Advanced Neutron Absorbing Material in the High Flux Isotope Reactor Conference Paper September, 2019