Phase Relationships in the Carbon–Titanium–Uranium System for Ultra-High Temperature Nuclear Fuels... Journal October, 2021
Implementation of a Drift-Flux Model in SAM for Modeling of Passively Transported GAS in Molten Salt Reactors ORNL Report October, 2021
Design Readiness And Maturity Assessment (DRAMA) Tool for Advanced Reactors... Conference Paper October, 2021
Development of an Activation Analysis Methodology to Support the Disposal of the High Flux Isotope Reactor Metal Pool Waste ORNL Report October, 2021
Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod... Conference Paper October, 2021
POST-TEST EXAMINATIONS OF A LOCA SAMPLE FROM AN IRRADIATED HIGH-BURNUP PWR M5 FUEL ROD... Conference Paper October, 2021
Investigation Into the Use of Machine Learning Assisted Prediction of Nodal Parameters for Reduced Order Neutronic Simulation Models Conference Paper October, 2021