Published July 1991
| Version v1
Report
Frequencies of leaks and breaks in safety related piping of PWR-plants as initiating events for LOCAs
Description
The analysis of the effects of LOCA events shows, that there are various ranges of leak rates that are to be distinguished corresponding to the capabilities of systems that are directed to assure the safe condition of the plant. The actuation and subsequent operation of these systems is a further barrier to prevent core damage. Other ranges apply for the steam generators. The frequency of some leak rates will be dominated by inadvertent or faulty opening actions of valves. Some LOCA-relevant leak rates however are mainly caused by wall-penetrating cracks or a break of a pipe. These damages in the walls of the primary coolant retaining system and their frequencies will be discussed here. (orig.)
Availability note (English)
Available from FIZ Karlsuhe.Additional details
Publishing Information
- ISBN
- 3-923875-36-3
- Imprint Title
- Proceedings of the OECD/BMU-workshop on special issues of level 1 PSA
- Imprint Pagination
- 407 p.
- Journal Page Range
- p. 364-380.
- Report number
- GRS--86
Conference
- Title
- OECD/BMU-workshop on special issues of level 1 PSA.
- Dates
- 27-29 May 1991.
- Place
- Cologne (Germany).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 23031928
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; ECCS; FRACTURES; LEAKS; LOSS OF COOLANT; PIPES; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS