Use for MELCOR in probabilistic safety assessments of level 2
Description
The objective of the Probabilistic Safety Assessment Level 2 (PSA L2) is to determine the radiological source term risk of a nuclear power plant (NPP) based on core melt frequencies calculated in the PSA L1. As long as the containment is intact a core melt accident does not result in a large release of radioactivity to the environment. However, in the course of the accident different phenomena may result in a loss of the confinement. The probabilities of different failure modes of the confinement and containment respectively are determined by a Containment Event Tree (CET). The quantification of the branch probabilities and the determination of the fission product source term are supported by integral deterministic analyses. For PSA L2 for German NPPs AREVA NP GmbH uses MELCOR for these integral deterministic analyses. In addition, dedicated Monte Carlo programs have been developed by AREVA [Pau 2007] to derive probabilistic numbers from the deterministic results and to address physical phenomena, which cannot be adequately simulated by MELCOR. This paper presents the general approach how MELCOR is used within the frame of the PSA L2 for German NPPs. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2008. Tagungsbericht
Publishing Information
- Publisher
- Inforum Verlag
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2008. Proceedings
- Imprint Pagination
- 886 p.
- Journal Page Range
- p. 258-263
Conference
- Title
- 2008 annual meeting on nuclear technology
- Original Conference Title
- Jahrestagung Kerntechnik (JK) 2008
- Dates
- 27-29 May 2008
- Place
- Hamburg (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42016965
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUTOHYDROLYSIS; CONTAINMENT; CORIUM; FAILURE MODE ANALYSIS; FEDERAL REPUBLIC OF GERMANY; FISSION PRODUCT RELEASE; HYDROGEN PRODUCTION; M CODES; MELTDOWN; MONTE CARLO METHOD; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; REACTOR ACCIDENT SIMULATION; RISK ASSESSMENT; SAFETY ANALYSIS; SOURCE TERMS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CHEMICAL REACTIONS; COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; DECOMPOSITION; DEVELOPED COUNTRIES; ENERGY SYSTEMS; EUROPE; HEAT TREATMENTS; HYDROLYSIS; LYSIS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; SIMULATION; SOLVOLYSIS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WESTERN EUROPE
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2008. Tagungsbericht