Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions Journal June, 2023
Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions Journal June, 2023
Frequency Response Analysis of the Molten Salt Demonstration Reactor Dynamic Simulation Model in Transient Simulation Framework of Reconfigurable Models (TRANSFORM) Conference Paper May, 2023
Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation–FY23 ORNL Report May, 2023
A Review of Advanced Test Reactor Fuel and Assessment of its Compatibility with the ZIRCEX Chlorination Process ORNL Report May, 2023
A novel protocol to recycle zirconium from zirconium alloy cladding from used nuclear fuel rods Journal May, 2023
Updated Recommendations Related to Spent Fuel Transport and Dry Storage Shielding Analyses ORNL Report May, 2023