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
LIGHT WATER REACTOR SUSTAINABILITY PROGRAM MATERIALS RESEARCH PATHWAY TECHNICAL PROGRAM PLAN ORNL Report January, 2023
A geospatial risk analysis graphical user interface for identifying hazardous chemical emission sources... Journal January, 2023
Extraordinary creep resistance in a non-equiatomic high-entropy alloy from the optimum solid-solution strengthening and stres... Journal January, 2023
Effects of Microstructural Composition, Porosity, and Microcracks on the Elastic Moduli of Nuclear Graphites Book Chapter December, 2022
Equibiaxial Flexure Strength of a Superfine-Grained Nuclear Graphite... Conference Paper December, 2022
A Microstructural Modeling-Based Approach to Graphite Oxidation beyond ASTM D7542... Book Chapter December, 2022