Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner

摘要

AbstractPrecipitation of radial hydrides in zirconium-based alloy cladding concomitant with the cooling of spent nuclear fuel during dry storage can potentially compromise cladding integrity during its subsequent handling and transportation.This paper investigates hydride reorientation and its impact on ductility in unirradiated and irradiated recrystallized Zircaloy-2 cladding with an inner liner (cladding for boiling water reactors) subjected to hydride reorientation treatments.Cooling from 400?°C, hydride reorientation occurs in recrystallized Zircaloy-2 with liner at a lower effective stress in irradiated samples (below 40?MPa) than in unirradiated specimens (between 40 and 80?MPa).Despite significant hydride reorientation, unirradiated recrystallized Zircaloy-2 with liner cladding containing ～200 wppm hydrogen shows a high diametral strain at fracture (>15%) during burst tests at ambient temperature. This ductile behavior is due to (1) the lower yield stress of the recrystallized cladding materials in comparison to hydride fracture strength (corrected by the compression stress arising from the precipitation) and (2) the hydride or hydrogen-depleted zone as a result of segregation of hydrogen into the liner layer.In irradiated Zircaloy-2 with liner cladding containing ～340 wppm hydrogen, the conservation of some ductility during ring tensile tests at ambient temperature after reorientation treatment at 400?°C with cooling rates of ～60?°C/h is also attributed to the existence of a hydride-depleted zone. Treatments at lower cooling rates (～6?°C/h and 0.6?°C/h) promote greater levels of hydrogen segregation into the liner and allow for increased irradiation defect annealing, both of which result in a significant increase in ductility.Based on this investigation, given the very low cooling rates typical of dry storage systems, it can be concluded that the thermal transients associated with dry storage should not degrade, and more likely should actually improve, ductility of recrystallized Zircaloy-2 cladding with inner liner with such hydrogen content.Highlights?Irradiation lowers the reorientation threshold stress of recrystallized Zircaloy-2.?In the unirradiated state, this cladding is highly ductile, even with radial hydrides.?In the irradiated state, ductility is affected by radial hydrides.?Low cooling rates favor hydrogen segregation into the liner, which increases ductility.?Irradiation defect annealing has a beneficial effect on cladding ductility.