Proceedings: 2000 EPRI Workshop on PWSCC of Alloy 600 in PWRs (PWRMRP-27)
Conference
·
OSTI ID:835291
Primary water stress corrosion cracking (PWSCC) can lead to increased costs for operation, maintenance, assessment, repair, and replacement of PWR components. This EPRI workshop emphasized issues related to PWSCC of reactor vessel (RV) closure head nozzles, including control rod drive mechanism (CRDM) nozzles, and other primary system alloy 600 penetrations.
- Research Organization:
- Electric Power Research Institute, Palo Alto, CA (US)
- Sponsoring Organization:
- Electric Power Research Institute (EPRI) (US)
- OSTI ID:
- 835291
- Report Number(s):
- EPRI--1000873
- Country of Publication:
- United States
- Language:
- English
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