The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts Journal February, 2023
Total thermal neutron cross section measurements of yttrium hydride from 0.0005 - 3 eV Journal February, 2023
A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes Journal February, 2023
Molybdenum-99 from Molten Salt Reactor as a Source of Technetium-99m for Nuclear Medicine: Past, Current, and Future of Molybdenum-99 Journal February, 2023
Enhancing Monte Carlo Workflows for Nuclear Reactor Analysis with Metamodel-Driven Modeling Journal February, 2023
Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding Journal February, 2023
