Journal Of Nuclear Materials

U3Si2 behavior in H2O environments: Part II, pressurized water with controlled redox chemistry

Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock

High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments

Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade

Irradiation effects in high entropy alloys and 316H stainless steel at 300 degrees C

Microstructure and thermal properties of unalloyed tungsten deposited by Wire plus Arc Additive Manufacture

Effects of Ti and Ta addition on microstructure stability and tensile properties of reduced activation ferritic/martensitic steel for nuclear fusion reactors

On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models

Separate effects irradiation testing of miniature fuel specimens

Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn plus Sb as a mixed additive system to bind lanthanides