Reactor vessel assessment and the development of a reactor vessel life extension program for Calvert Cliffs Units One and Two
Creators
- 1. Baltimore Gas and Electric Co., Calvert Cliffs Nuclear Power Plant, Lusby, MD (USA)
- 2. Combustion Engineering Inc., 1000 Prospect Hill Road, Windsor, CT (USA)
Description
A study has been undertaken to provide a general assessment of the life extension capabilities for the Calvert Cliffs Units One and Two reactor pressure vessels. The purpose of the study is to assess the general life extension capabilities for the Calvert Cliffs reactor pressure vessels based upon an extension and variation of the Surry pilot plant life extension study. This assessment provided a detailed reactor vessel surveillance program for plant life extension along with a hierarchy of specific tasks necessary for attaining maximum useful life. The assessment identified a number of critical issues which may impact life attainment and extension along with potential solutions to address these issues to ensure the life extension option is not precluded
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-139-8
- Imprint Title
- Proceedings of the topical meeting on nuclear power plant life extension
- Imprint Pagination
- 645 p.
- Journal Page Range
- p. 205-209.
Conference
- Title
- American Nuclear Society (ANS) topical meeting on nuclear power plant life extension.
- Dates
- 31 Jul - 3 Aug 1988.
- Place
- Snowbird, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22056024
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALVERT CLIFFS-1 REACTOR; CALVERT CLIFFS-2 REACTOR; LIFETIME; MONITORING; PERFORMANCE TESTING; REACTOR VESSELS
- Descriptors DEC
- CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-880748--.