An approach to merge PSA-based assumptions and BEPU method - 15556
Creators
- 1. Departamento de Ingenieria Quimica y Nuclear - Universitat Politecnica de Valencia, Cami de Vera s/n, 46022 Valencia (Spain)
Description
The adoption by regulators of the risk-informed decision-making philosophy has opened the debate on the role of the deterministic and probabilistic approaches to support regulatory matters of concern to Nuclear Power Plants (NPP) safety. In this respect, a related medium-term challenge is to combine the use of well established Best Estimate Plus Uncertainty (BEPU) methodology and probabilistic-based assumptions on systems availability as proposed in option 4 IAEA SSG-2 guide (DSA for NPP Specific Safety Guide, No. SSG-2). In this paper, an approach is proposed to integrate probabilistic assumptions on the availability of safety systems into deterministic safety assessment, which follows and extends the fundamentals of the BEPU methods to build an Extended BEPU method that follows the principles of option 4 of the above guide. An example of application is provided to demonstrate how this approach performs. The case study focuses on an accident scenario following the initiating event 'Loss Of Feed Water (LOFW)' for a typical three-loops Pressurized Water Reactor (PWR) NPP
Availability note (English)
Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 3246-3253
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49010214
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DETERMINISTIC ESTIMATION; LOSS OF COOLANT; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT; SAFETY MARGINS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.