Uncertainty and sensitivity methods in support of PSA level 2
Creators
- 1. CEA Cadarache, Dept. d'Etudes des Reacteurs, Service d'Etudes des Systemes Innovants (SESI), 13 - Saint-Paul-lez-Durance (France)
- 2. Nuclear safety Unit, Institute for energy - Joint Research Centre, European Commission, Petten (Netherlands)
Description
Dealing with uncertainties in PSA level 2 requires using a set of statistical techniques to assess input uncertainty, to propagate uncertainties in an efficient way, to characterize appropriately output uncertainty and to get information from computer code runs through an intelligent use of sensitivity analysis techniques. The purpose of this paper is to give an overview of statistical and probabilistic methods and tools to answer to these topics, and to provide some guidance about their suitability and limitations to be used in a PSA level 2. Our position about their implementation in L2 PSA software has been written; it could be noticed that a lot of these methods are very time-consuming, and seem more suitable for the analysis of submodels or for focusing on specific questions. (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. 234-279
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
- 39033924
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA COVARIANCES; DETERMINISTIC ESTIMATION; FAILURE MODE ANALYSIS; MONTE CARLO METHOD; PROBABILISTIC ESTIMATION; RANDOMNESS; REACTOR SAFETY; RELIABILITY; SENSITIVITY ANALYSIS; STATISTICS; VALIDATION
- Descriptors DEC
- CALCULATION METHODS; MATHEMATICS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING
Optional Information
- Notes
- 24 refs.