Fuzzy reliability algorithm for the shutdown system of research reactor
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Hala K. G. Selim
Abstract
Probabilistic safety assessment (PSA) has been applied to evaluate the safety of nuclear reactor systems. The results of PSA are used by designers, utilities and regulatory body to confirm the reactor design, to change operation procedures, to enhance the reliability of safety systems, or to modify regulation. Fault tree analysis (FTA) has been used as a deductive means for PSA. System components are assumed to always have defined failure probabilities; however, in reality this assumption is questionable and sometimes there is insufficient data about the failure probability of some components. To solve this problem, fuzzy approaches have been proposed and implemented. The aim of this study is to apply a fuzzy reliability algorithm to estimate basic events failure probabilities for the shutdown system of a research reactor. The reactor is a 22 MW light water open pool type material test reactor and the shutdown system is responsible for the fast shutdown of the reactor whenever safety limits are exceeded. Then, to illustrate the ability of the algorithm, the results are compared with real basic event failure probabilities. The results verify the competence of the algorithm and confirm that it can be applied as an alternative method when quantitative data are not available. Also, a risk importance measure is done on the fault tree of the shutdown system to illustrate which components need to be focused for improvements to achieve the safe operation of shutdown system.
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Research ethics: Not applicable.
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Author contributions: The author has accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: There are no conflicts of interest associated with this work.
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Research funding: None declared.
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Data availability: Data available on request.
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Articles in the same Issue
- Frontmatter
- Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
- Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
- Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)
- A detection and defense security system design for nuclear waste storage against stealth terrorists attack
- Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation
- Fuzzy reliability algorithm for the shutdown system of research reactor
- System theory safety analysis of network malfunction in nuclear power plant distributed control systems
- Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction
- Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
- Reliability analysis of digital reactor protection systems in floating nuclear power plants
- Study on comprehensive evaluation method of mental workload level
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