Thermal creep behavior of hydrogen-enriched Zr1%Nb alloy fuel cladding tube in phase transit regions
Václav Sklenička, Marie Kvapilová, Pétr Král, Jiri Dvorak
Among various degradation processes, thermal creep is considered a life-limiting factor for zirconium nuclear fuel cladding in light water reactors. In this work, the creep behavior of pre-oxidized and pre-hydrided in steam thin-walled Zr1wt.%Nb alloy fuel cladding tube was investigated in α-Zr …
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Journal of Nuclear Materials