Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
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Elena D. Morlova
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Daniela Mladin
Abstract
Probabilistic Safety Assessment is a tool for improving a nuclear installation and its safety in all its function phases. PSA provides a methodical way of identifying sequences resulting from a wide range of initiating events concerning an accident, and includes systematic and realistic determination of accident frequencies and their consequences. This paper analyzes the unavailability of the TRIGA SSR reactor primary circuit, obtaining the system unavailability value, identifying main contributors to system failure, and calculating risk importance factors. Two cases were considered: one without considering Common Cause Failure (CCF) in the developed fault tree, and the second considering CCF on pumps and heat exchangers lines. The aim was to assess their influence on the primary system’s unavailability. Two importance factors, Fussell–Vesely and Risk Achievement Worth, were employed to identify components with a strong impact on the risk (probability of system failure). These factors aid in enhancing maintenance activities and testing. The analysis utilized the EDFT code, part of the PSAMAN code package developed in SCN-Pitesti.
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Research ethics: The local Institutional Review Board deemed the study exempt from review.
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Informed consent: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interests: The authors state no conflict of interest.
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Research funding: None declared.
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Data availability: Not applicable.
References
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© 2024 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events
