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Identification of Risk-Significant Components in Nuclear Power Plants to Reduce Cs-137 Radioactive Risk

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  • Cho, Jaehyun
  • Han, Sang Hoon

Abstract

The amount and frequency of Cs-137 release in a nuclear accident are regulated to enhance environmental radiation protection. While significant improvements have been accomplished, including the preparation of severe accident mitigation equipment and systems to satisfy Cs-137 regulations, no attempt has yet been made along these lines to manage the structures, systems and components (SSCs) in nuclear power plants. Therefore, this paper proposes a new approach to identify the significant SSCs by quantifying related risk importance measures using release frequency and Cs-137 radioactivity. The new approach includes a Level 1 and Level 2 probabilistic safety assessment (PSA) linked model to obtain the frequency and Cs-137 radioactivity in all accident scenarios. The developed approach was applied to an OPR-1000 full-power internal events PSA model, and as a result, the top 20 SSCs were identified based on Fussell–Vesely importance, risk reduction worth, and risk achievement worth measures. The new approach can support risk-informed management for not only Cs-137 regulations but also public risk by using early and latent cancer fatalities.

Suggested Citation

  • Cho, Jaehyun & Han, Sang Hoon, 2021. "Identification of Risk-Significant Components in Nuclear Power Plants to Reduce Cs-137 Radioactive Risk," Reliability Engineering and System Safety, Elsevier, vol. 211(C).
    • Handle: RePEc:eee:reensy:v:211:y:2021:i:c:s0951832021001587
    DOI: 10.1016/j.ress.2021.107613
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    References listed on IDEAS

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    3. Silva, Kampanart & Okamoto, Koji, 2018. "Discussion on probability of cesium-137 release exceeding 100 TBq as a part of the consideration of nuclear power plant probabilistic risk criteria for environmental protection," Reliability Engineering and System Safety, Elsevier, vol. 180(C), pages 88-93.
    4. Kim, Jaewhan & Cho, Jaehyun, 2020. "Technical challenges in modeling human and organizational actions under severe accident conditions for Level 2 PSA," Reliability Engineering and System Safety, Elsevier, vol. 194(C).
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    Cited by:

    1. Cho, Jaehyun & Lee, Sang Hun & Kim, Jaewhan & Park, Seong Kyu, 2022. "Framework to model severe accident management guidelines into Level 2 probabilistic safety assessment of a nuclear power plant," Reliability Engineering and System Safety, Elsevier, vol. 217(C).
    2. Cho, Jaehyun & Lee, Sang Hun & Bang, Young Suk & Lee, Suwon & Park, Soo Yong, 2022. "Exhaustive simulation approach for severe accident risk in nuclear power plants: OPR-1000 full-power internal events," Reliability Engineering and System Safety, Elsevier, vol. 225(C).
    3. Kowal, Karol, 2022. "Lifetime reliability and availability simulation for the electrical system of HTTR coupled to the electricity-hydrogen cogeneration plant," Reliability Engineering and System Safety, Elsevier, vol. 223(C).

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