Effects of Radial Hydrides on PWR Cladding Ductility following Drying and Storage
- Argonne National Lab. (ANL), Argonne, IL (United States)
The purpose of this research effort is to determine the effects of canister and/or cask drying, transfer and storage on radial hydride precipitation in, and potential embrittlement of, high-burnup (HBU) pressurized water reactor (PWR) cladding alloys during cooling for a range of peak drying-storage temperature (PCT) values and hoop stresses. Extensive radial-hydride precipitation could lower failure hoop stresses and strains, relative to limits established for as-irradiated cladding from discharged fuel rods, at temperatures below the ductility transition temperature (DTT), which has been referred to as the ductile-to-brittle transition temperature (DBTT) in previous reports. During post-storage transport, hoop stresses will be induced by “pinch -type” loading at grid spacers. Such loading is considered to be mild for normal conditions of transport and more severe for hypothetical accident conditions.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5). Fuel Cycle Research and Development
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1478471
- Report Number(s):
- SFWD-SFWST-2017-000001; 139191
- Country of Publication:
- United States
- Language:
- English
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