A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes... Journal February, 2023
Weldability of irradiated Stainless Steel 304 materials harvested from the National Research Universal (NRU) reactor... Journal February, 2023
Microstructural heterogeneity of the buffer layer of TRISO nuclear fuel particles... Journal February, 2023
High-temperature oxidation behavior of the SiC layer of TRISO particles in low-pressure oxygen... Journal February, 2023
Molybdenum-99 from Molten Salt Reactor as a Source of Technetium-99m for Nuclear Medicine: Past, Current, and Future of Molyb... Journal February, 2023
Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding Journal February, 2023
HIGH-LOW FIDELITY THERMAL HYDRAULIC COUPLING USING AI/MACHINE LEARNING ALGORITHMS Conference Paper February, 2023
Computational modeling and validation of a modified Marple cascade impactor Conference Paper February, 2023