Fuzzy PSA evaluation method for passive residual heat removal system
Creators
- 1. Institute of Nuclear Thermal-Hydraulic Safety and Standardization, North China Electric Power University, Beijing 102206 (China)
Description
Highlights: ► We build the fuzzy PSA evaluation model of passive heat removal system. ► We modified the traditional PSA method, especially introducing the clustering to derive expert weight coefficient. ► We give more conservative estimation for top event failure with almost all the states of events are concerned. - Abstract: Fuzzy quantification evaluation is one of the most effective ways to solve the factors' uncertainty in the nuclear power station PSA. Take AP1000 passive residual heat removal system for example, a modified fuzzy PSA calculation model is established, in which two important conceptions membership and weight are introduced. The top events probability is finally calculated by the matrix quantification way. The results show that, fuzzy PSA method is suitable for the conservative estimation of failure probability, in which the relativity between different factors and the uncertainty of their own property are both considered. Meanwhile, it can provide a comprehensive evaluation of event failure and make an overall description of the real situation, especially for conservative estimation. It gives a new calculation method for nuclear PSA research.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.03.007Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.03.007;
- PII
- S0029-5493(12)00120-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 247
- Journal Page Range
- p. 230-235
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43078856
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- AFTER-HEAT REMOVAL; CALCULATION METHODS; FAILURES; FUZZY LOGIC; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RHR SYSTEMS; SAFETY ANALYSIS
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; ENERGY SYSTEMS; MATHEMATICAL LOGIC; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REMOVAL; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.