Documentation Package Supporting Fabrication of Doped UO2 Samples for MiniFuel Irradiation and Fission Gas Release Benchmarking ORNL Report June, 2019
Measurement and modeling of the gas permeability of high burnup pressurized water reactor fuel rods Journal June, 2019
Features that further Performance Limits of Nuclear Fuel Fabrication: Opportunities for Additive Manufacturing of Nuclear Fuels ORNL Report June, 2019
Purification of industrial grade lithium chloride for the recovery of high purity battery grade lithium carbonate Journal May, 2019
Separate Effects Miniature Fuel Irradiation Testing to Support Fuel Safety Conference Paper May, 2019
Tensile Testing and Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels at the IMET Hot Cell and Lambda Facilities ORNL Report May, 2019
Full-core analysis for FeCrAl enhanced accident tolerant fuel in boiling water reactors Journal May, 2019
Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration Journal May, 2019