Understanding the effect of specimen size on the properties of fine-grain isotropic nuclear graphite for irradiation studies: Mechanical properties Journal April, 2023
Understanding the effect of specimen size on the properties of fine-grain isotropic nuclear graphite for irradiation studies: Physical, electrical, thermal properties Journal April, 2023
Codes and standards for ceramic composite core materials for High Temperature Reactor applications Journal April, 2023
Influence of fatigue precracking and specimen size on Master Curve fracture toughness measurements of EUROFER97 and F82H steels Journal March, 2023
The response of accident tolerant fuel cladding to LOCA burst testing: A comparative study of leading concepts Journal February, 2023
Weldability of irradiated Stainless Steel 304 materials harvested from the National Research Universal (NRU) reactor Journal February, 2023
Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding Journal February, 2023
On the thermal oxidation of nuclear graphite relevant to high-temperature gas cooled reactors Journal January, 2023
