Updating risk model for SGTR accident based on success criteria analysis
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Meisam Mohammadnia
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Kaveh Karimi
Abstract
Success criteria analysis plays a key role in the development of realistic probabilistic safety/risk assessment (PSA/PRA) model because it provides supporting information regarding the response of complex nuclear power plant systems to different accident conditions. The current paper performs plant specific success criteria analysis for steam generator tube rupture (SGTR) accident in a typical pressurized water reactor (PWR) and demonstrates implementation of the obtained best estimate results on a risk model which has been initially developed based on expert judgment and general plant design data. The modifications on the risk model include configuration of the safety systems as well as the event tree structure. The updated PSA model shows 50% reduction in the plant core damage frequency (CDF) in comparison to the base case risk model. This highlights the importance of success criteria analysis for the development of a realistic PSA model in risk informed applications.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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© 2022 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
- Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
- Updating risk model for SGTR accident based on success criteria analysis
- The analysis of fire ignition frequency calculation for small modular light water reactors
- New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
- Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
- Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
- The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
- Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Experimental investigation of thermal characteristics of a cylindrical heat pipe under varied system parameters and operating conditions
- Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)
- Updating risk model for SGTR accident based on success criteria analysis
- The analysis of fire ignition frequency calculation for small modular light water reactors
- New flow boiling frictional pressure drop multipliers for smooth and microfin tubes
- Steady state thermal hydraulic modelling of WWR-S tank-in-pool research reactor for the purpose of its power upgrading
- Computational study of subcooled water injection into steam line: effect of Reynolds number on flow transition to study condensation induced water hammers
- The investigation of heat transfer enhancement by using different mixture conditions of graphene nanofluids on a downward facing surface
- Corrigendum to: Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Calendar of events
