Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)
- EPRI
Pressurized water reactor (PWR) cores, operate under extreme environmental conditions due to coolant chemistry, operating temperature, and neutron exposure. Extending the life of PWRs require detailed knowledge of the changes in mechanical and corrosion properties of the structural austenitic stainless steel components adjacent to the fuel. This report contains basic material characterization information of the as-installed samples of reactor internals material which were harvested from a decommissioned PWR.
- Research Organization:
- EPRI (US)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
- DOE Contract Number:
- FC07-00NE22796
- OSTI ID:
- 836105
- Report Number(s):
- 1009799
- Country of Publication:
- United States
- Language:
- English
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