Life cycle considerations for pressurized water reactor vessels
Description
This paper reports on the pressurized water reactor (PWR) reactor vessel identified by the Surry 1 life extension project as a critical element for life extension considerations. This ranking was based on a prioritization of all the plant systems, components, and structures taking into account difficulty to repair/replace and wear out considerations. The study also determined the vessel has a high probability for extended service life based on best estimate analysis of actual usage, maintenance, in-service inspection programs, and presently available methods for prolonging vessel life. Feasibility studies have also been performed for PWR reactor pressure vessels designed by the three domestic vendors. All of these studies concluded that the reactor vessel has a high probability for extended service life beyond the original license period
Additional details
Publishing Information
- Journal Title
- Proceedings of the American Power Conference
- Journal Volume
- 53
- Series
- Proc. Am. Power Conf.
- Journal Page Range
- 184-185
- ISSN
- 0097-2126
- CODEN
- PAPWA
Conference
- Title
- 53. annual American power conference.
- Dates
- 29 Apr - 1 May 1991.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23015036
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FEASIBILITY STUDIES; IN-SERVICE INSPECTION; LIFETIME; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR VESSELS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; INSPECTION; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9104106--.