Published December 1984
| Version v1
Report
Steam generator tube rupture risk impact on design and operation of French PWR plants
Creators
- 1. Electricite de France, 69 - Villeurbanne. Service Etudes et Projets Thermiques et Nucleaires
Description
The experience of steam generator tube leaks incidents in PWR plants has resulted in an increase of EDF analysis leading to improvements in design and post-accidental operation for new projects and operating plants. The accident consequences are minimized for each of the NSSS three barriers: first barrier: safeguard systems design and operating procedures relying upon core safety allow to maintain a low level of primary radioactivity, second barrier: steam generator design and periodic inspection allow to reduce tube ruptures risks and third barrier: atmospheric releases are reduced as a result of optimal recovery procedures, detection improvements and atmospheric steam valves design improvements. (orig.)
Additional details
Publishing Information
- Imprint Title
- 5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 1
- Imprint Pagination
- 761 p.
- Journal Page Range
- p. 581-587.
- Report number
- KFK--3880/1
Conference
- Title
- 5. international meeting on thermal nuclear reactor safety.
- Dates
- 9-13 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 16068483
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN BASIS ACCIDENTS; FISSION PRODUCT RELEASE; FRANCE; IN-SERVICE INSPECTION; LEAKS; PWR TYPE REACTORS; RUPTURES; STEAM GENERATORS; TUBES
- Descriptors DEC
- ACCIDENTS; BOILERS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; FAILURES; INSPECTION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS