Investigations concerning fire-induced accidents in nuclear facilities
- 1. CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire
Description
In the context of fire protection in technical buildings of French nuclear facilities, three principles have been adopted: prevention, detection and fire-fighting. Their implementation makes it possible on the one hand to limit the fire ignition and the fire growth, and on the other hand to prevent fire extent which would lead to unavailability of several safety related equipment. Although progress has been made in this direction, the fire risks have still not been eliminated. It is therefore essential to evaluate the fire effects and to assess their consequences. To this end, three main R and D programs have been conducted into fires. Part I sets out the fire PSA methodology used for a 900 MWe PWR. Part II gives an outline of two fire and ventilation computer codes useful for the fire PSA. Finally, part III gives an outline of the tests already performed and those currently under way in the two laboratories of the Institut de Protection et de Surete Nucleaire (IPSN) in order to qualify the codes and provide useful information for the safety assessment. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the first NUCEF international symposium (NUCEF'95). Engineering safety of nuclear fuel cycle facility
- Imprint Pagination
- 231 p.
- Journal Page Range
- p. 132-141.
- Report number
- JAERI-Conf--96-003
Conference
- Title
- 1. NUCEF international symposium.
- Acronym
- NUCEF'95
- Dates
- 16-17 Oct 1995.
- Place
- Hitachinaka, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28001907
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; F CODES; FIRE DETECTORS; FIRE PREVENTION; FIRES; MATHEMATICAL MODELS; MELTDOWN; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; QUALITY ASSURANCE; RISK ASSESSMENT; SAFETY ANALYSIS; VENTILATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; MEASURING INSTRUMENTS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS