Uncertainty of the level 2 PSA for NPP PAKS
- 1. VEIKI Institute for Electric Power Research, Budapest (Hungary)
Description
In the Level 1 PSA for internal initiators and internal hazards of Paks NPP 60 initiating events starting from nominal power operation were studied and over 500 sequences were found to lead to 'core damage' end state. As the Level 2 PSA is based on the Level 1 PSA, Level 2 PSA also covers all the internal technological events occurring at nominal power and shut down states and also the influence of fire and flooding at nominal power. This paper is a short summary of the uncertainty analyses performed so far within the level 2 PSA for NPP Paks. Some important analysis steps and methods are highlighted with examples of results obtained. The uncertainty in containment failure state frequencies for NPP Paks is in the focus of attention in this paper. (authors)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency - Committee on the Safety of Nuclear Installations
- Imprint Place
- Paris (France)
- Imprint Title
- Evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis
- Imprint Pagination
- 1002 p.
- Journal Page Range
- p. 692-716
Conference
- Title
- Workshop proceedings evaluation of uncertainties in relation to severe accidents and level-2 probabilistic safety analysis
- Dates
- 7-9 Nov 2005
- Place
- Aix-en-Provence (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 39033936
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CONTAINMENT; CORIUM; DATA COVARIANCES; ECCS; FAILURE MODE ANALYSIS; HYDROGEN; MELTDOWN; MONTE CARLO METHOD; PROBABILISTIC ESTIMATION; SENSITIVITY ANALYSIS; VALIDATION
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ELEMENTS; ENGINEERED SAFETY SYSTEMS; NONMETALS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING
Optional Information
- Notes
- 4 refs.