Corrosion and Hydriding Performance Evaluation of Three Zircaloy-2 Clad Fuel Assemblies after Continuous Exposure in PWR Cores 1 and 2 at Shippingport, PA. Addendum. LWBR Development Program

摘要

The cladding from one additional Zircaloy-2 clad fuel rod from the pressurized water reactor at Shippingport, Pa. was destructively examined for corrosion film thickness and hydrogen accumulation. These additional examinations were conducted primarily to determine whether or not the hydrogen pickup ratio ( delta H/ delta O) increased with increasing neutron exposure, as had been suggested by the results from earlier studies on these fuel rods. The current results indicate that the hydrogen pickup ratio for Zircaloy-2 does not change with increasing neutron exposure and suggest that some of the earlier reported data may be anomolous. (ERA citation 09:013754)