Effects of Lower Drying-Storage Temperature on the Ductility of High-Burnup PWR Cladding
- 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 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 temperatures (PCT) and hoop stresses. Extensive precipitation of radial hydrides could lower the failure hoop stresses and strains, relative to limits established for as-irradiated cladding from discharged fuel rods stored in pools, at temperatures below the ductile-to-brittle transition temperature (DBTT).
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1326598
- Report Number(s):
- FCRD-UFD-2016-000065; 130080; TRN: US1700297
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effects of Radial Hydrides on PWR Cladding Ductility following Drying and Storage
Effects of Lower Drying-Storage Temperatures on the DBTT of High-Burnup PWR Cladding
Used Fuel Disposition Campaign - Baseline Studies for Ring Compression Testing of High-Burnup Fuel Cladding
Technical Report
·
Sun Jan 01 00:00:00 EST 2017
·
OSTI ID:1326598
Effects of Lower Drying-Storage Temperatures on the DBTT of High-Burnup PWR Cladding
Technical Report
·
Fri Aug 28 00:00:00 EDT 2015
·
OSTI ID:1326598
Used Fuel Disposition Campaign - Baseline Studies for Ring Compression Testing of High-Burnup Fuel Cladding
Technical Report
·
Fri Nov 23 00:00:00 EST 2012
·
OSTI ID:1326598
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
PWR TYPE REACTORS
FUEL CANS
DUCTILITY
DRYING
SPENT FUEL STORAGE
SPENT FUEL CASKS
HYDRIDES
PRECIPITATION
STRESSES
COOLING
EMBRITTLEMENT
FAILURES
TEMPERATURE DEPENDENCE
STRAINS
TEMPERATURE RANGE 0400-1000 K
PRESSURE RANGE MEGA PA 10-100
Cladding integrity
Spent fuel
radial hydrides
storage
36 MATERIALS SCIENCE
PWR TYPE REACTORS
FUEL CANS
DUCTILITY
DRYING
SPENT FUEL STORAGE
SPENT FUEL CASKS
HYDRIDES
PRECIPITATION
STRESSES
COOLING
EMBRITTLEMENT
FAILURES
TEMPERATURE DEPENDENCE
STRAINS
TEMPERATURE RANGE 0400-1000 K
PRESSURE RANGE MEGA PA 10-100
Cladding integrity
Spent fuel
radial hydrides
storage