skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods (LWBR Development Program)

Technical Report ·
DOI:https://doi.org/10.2172/5417409· OSTI ID:5417409

Twenty-one LWBR irradiation test rods containing ThO/sub 2/-UO/sub 2/ fuel and Zircaloy cladding with holes or cracks operated successfully. Zircaloy cladding corrosion on the inside and outside diameter surfaces and hydrogen pickup in the cladding were measured. The observed outer surface Zircaloy cladding corrosion oxide thicknesses of the test rods were similar to thicknesses measured for nondefected irradiation test rods. An analysis model, which was developed to calculate outer surface oxide thickness of non-defected rods, gave results which were in reasonable agreement with the outer surface oxide thicknesses of defected rods. When the analysis procedure was modified to account for additional corrosion proportional to fission rate and to time, the calculated values agreed well with measured inner oxide corrosion film values. Hydrogen pickup in the defected rods was not directly proportional to local corrosion oxide weight gain as was the case for non-defected rods. 16 refs., 6 figs., 8 tabs.

Research Organization:
Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States)
DOE Contract Number:
AC11-76PN00014
OSTI ID:
5417409
Report Number(s):
WAPD-TM-1393; ON: DE85017355
Country of Publication:
United States
Language:
English