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Neutron Irradiation of Hydrided Cladding Material in HFIR Summary of Initial Activities

Irradiation is known to have a significant impact on the properties and performance of Zircaloy cladding and structural materials (material degradation processes, e.g., effects of hydriding).  This UFD study examines the behavior and performance of unirradiated cladding and actual irradiated cladding through testing and simulation.  Three capsules containing hydrogen-charged Zircaloy-4 cladding material have been placed in the High Flux Isotope Reactor (HFIR). Irradiation of the capsules was conducted for post-irradiation examination (PIE) metallography.