2024, Vol.27, No.1, pp.69 - 77
Probabilistic safety analysis of loss of coolant accidents (LOCA) in the VVER-reactor plant has been performed, taking into account the internal initiating events of the reactor primary circuit middle leakages. Logical probabilistic models of the accident scenarios of the middle primary circuit leakages were developed taking into account different operation modes of reactor plant. Critical paths and probabilities of the accident scenarios were identified. Program code RiskSpectrum PSA was used for probabilistic safety analysis. Recommendations for increase of reliability of systems safety functions during the middle leakages accidents were given.
Key words: probabilistic safety assessment, safety of nuclear power plant, accident scenarios
DOI: https://doi.org/10.5281/zenodo.10889768
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