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Systematic approach and mathematical development for conditional core damage probabilities under station blackout of a nuclear power plant

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  • Kim, Man Cheol

Abstract

Station blackout (SBO), a total loss of alternating current (AC) power, is considered to contribute significantly to nuclear power plant risk. The analysis of SBO risk is complicated due to time-dependent interactions among events. Simplifying assumptions that are currently used extensively in probabilistic safety assessment may lead to an overly conservative estimation of SBO risk, which may distort the overall plant risk profile and the associated accident management strategy. To calculate more accurate SBO risk, this study first identified SBO sequences and the associated time-dependent interactions by differentiating fail-to-start and fail-to-run failures of alternative AC power source and turbine-driven pumps. Mathematical formulas were developed to calculate the conditional core damage probabilities corresponding to the identified SBO sequences. These mathematical formulas were verified via a Monte Carlo simulation. This study is expected to contribute to the development of an integrated framework for SBO risk analysis that includes all possible SBO sequences, related events, and their time-dependent interactions.

Suggested Citation

  • Kim, Man Cheol, 2022. "Systematic approach and mathematical development for conditional core damage probabilities under station blackout of a nuclear power plant," Reliability Engineering and System Safety, Elsevier, vol. 217(C).
  • Handle: RePEc:eee:reensy:v:217:y:2022:i:c:s0951832021004804
    DOI: 10.1016/j.ress.2021.107969
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    References listed on IDEAS

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    1. Picoco, Claudia & Rychkov, Valentin & Aldemir, Tunc, 2020. "A framework for verifying Dynamic Probabilistic Risk Assessment models," Reliability Engineering and System Safety, Elsevier, vol. 203(C).
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    3. Hamza, Mostafa & Joslin, Nick & Lawson, Glen & McSweeney, Luke & Liao, Huafei & Vivanco, Alaina & Diaconeasa, Mihai A., 2024. "Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors," Reliability Engineering and System Safety, Elsevier, vol. 242(C).

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