Jason L Schulthess

Mechanical properties of irradiated U Mo alloy fuel

Jason L Schulthess, W.R. Lloyd, B.H. Rabin et al. · Journal of Nuclear Materials · 2018 · 31 citations · Full text

Materials Engineering, Materials Science, Nuclear Ceramic +4

Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT

Jason L Schulthess, Nicolas Woolstenhulme, Aaron E. Craft et al. · Journal of Nuclear Materials · 2020 · 22 citations · Full text

Radiation Effect, Radiation Exposure, Radiation Dose +5

Effect of fission rate on the microstructure of coated UMo dispersion fuel

A. Leenaers, Y. Parthoens, Gustaaf Cornelis et al. · Journal of Nuclear Materials · 2017 · 17 citations · Full text

Materials Science, Nuclear Ceramic, Chemical Engineering +5

Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions

Jason L Schulthess, David Kamerman, Alexander Winston et al. · Journal of Nuclear Materials · 2022 · 16 citations · Full text

Materials Engineering, Materials Science, Uranium Silicide Fuel +6

Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes

David Kamerman, Fabiola Cappia, K.R. Wheeler et al. · Nuclear Materials and Energy · 2022 · 16 citations · Full text