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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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All sourcesNASA NTRSDOE OSTI
DOE OSTI2023

AUSTENITIC STAINLESS STEEL WELD EMBRITTLEMENT BY HYDROGEN AND TRITIUM

-Commercialization of fusion power requires large scale, local re processing of D/T fuel, with throughputs ~1/6 of current global tritium supply per plant per day -Tritium is a radioactive material that has special needs in handling, processing, and storage -Tritium’s effects on the safety performance of primary pressure boundary materials (likely austenitic stainless steel) will be important for regulatory acceptance

KRENTZ, TIMOTHY M.↗
DOE OSTI2020

Improving Ductility of Hydride Embrittled Zirconium (Final Report)

One of the main limiting factors on the lifetimes of nuclear fuel rod claddings is the formation of hydrides and associated detrimental effects on mechanical properties. In this study, we examined the behavior of hydrides in zirconium and zircaloy-4 after tensile stress is applied to determine whether the more ductile γ-ZrH phase was stabilized by the mechanical stress. We did not find a significant increase in the ratio of γ-ZrH phase to δ-ZrH1.5 phases after tensile stress is applied in previously hydrided metals. Previous reports indicate that this stabilization does occur when zircaloy is stressed and hydrided simultaneously, indicating that the formation of the γ-ZrH phase may reverse upon relaxation or may require the stress in-situ during the hydriding process to form in significant quantities.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗