Condition-based probabilistic safety assessment of a spontaneous steam generator tube rupture accident scenario
- 1. Energy Department, Politecnico di Milano, Via La Masa 34, 20156 Milano (Italy)
- 2. Chair on System Science and Energetic Challenge, Fondation Electricite de France (EDF), CentraleSupelec, Université Paris Saclay, Grande Voie des Vignes, 92290 Châtenay-Malabry (France)
Description
Highlights: • PSA analyzes vulnerabilities of complex systems and quantify risk. • We present a Condition-Based PSA for augmenting PSA capabilities. • CB-PSA makes use of the information made available by sensors and/or inspections. • We demonstrate the CB-PSA on a spontaneous Steam Generator Tube Rupture accident. • The novel approach overcomes the results of a conventional PSA. - Abstract: Condition-Based Probabilistic Safety Assessment (CB-PSA) makes use of the information made available during operation by sensors and/or inspections on the state of components and systems. This allows specializing the PSA to the conditions of the components and systems, reducing the uncertainty on the risk measures quantified. In this paper, we demonstrate the CB-PSA with reference to a spontaneous Steam Generator Tube Rupture (SGTR) accident scenario in a Pressurized Water Reactor (PWR). Results show that the updated risk measures are capable of reflecting the actual state of the SG in the tailored risk evaluation.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2017.10.020Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2017.10.020;
- PII
- S0029549317304995;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 326
- Journal Page Range
- p. 41-54
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50070948
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- HEALTH HAZARDS; OCCUPATIONAL SAFETY; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT; STEAM GENERATOR TUBE RUPTURE; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; HAZARDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.