Influence of a high pressure injection system on the large break loca event tree
- 1. Institut Jozef Stefan, Ljubljana (Yugoslavia)
Description
Performing a Level 1 PSA analysis for the Krsko NPP, the authors have constructed an event tree for a large break loss of coolant accident (LOCA) according to assumptions in the Final Safety Analysis Report. Because of conservative assumptions one complete emergency core cooling system train is necessary to mitigate the consequences. On the basis of a deterministic conservative analysis, the authors have, however, tried to find out what the minimum success criteria requirement would be. In the first part of the analysis, the influence of high pressure injection on the large break LOCA transient has been tested. It was shown that the cladding temperatures without high pressure safety injection (HPSI) system were approximately 50 K higher than with HPSI operating. The second part of the analysis showed that, for the worst case combination of plugging, which for Krsko NPP is 10% plugging and 35% break size, the peak cladding temperature exceeds the allowed limit of 1478 K. The lesson learnt is that the plugging of steam generators demands HPSI to mitigate a large break LOCA. (author). 3 refs, 4 figs
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-000292-7
- Imprint Title
- Use of probabilistic safety assessment for operational safety. PSA '91
- Imprint Pagination
- 859 p.
- Series
- Proceedings series.
- Journal Page Range
- p. 405-412.
- ISSN
- 0074-1884
Conference
- Title
- International symposium on the use of probabilistic safety assessment for operational safety.
- Dates
- 3-7 Jun 1991.
- Place
- Vienna (Austria).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 23044239
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURE MODE ANALYSIS; HIGH PRESSURE COOLANT INJECTIO; KRSKO REACTOR; LOSS OF COOLANT; PROBABILISTIC ESTIMATION; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; ECCS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--321/34.