Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification Journal April, 2023
BISON analysis of FeCrAl and Zircaloy cladding deformation during simulated BWR cyclic dryout conditions Journal April, 2023
Fission gas retention of densely packed uranium carbonitride tristructural-isotropic fuel particles in a 3D printed SiC matrix Journal March, 2023
Summary of Methodology for Mitigating Risks Associated with Licensing and Qualifying AM Nuclear Materials ORNL Report March, 2023
The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts Journal February, 2023
A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes Journal February, 2023
