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Evaluation of the offsite dose contribution to the global risk in a Steam Generator Tube Rupture scenario

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  • Rebollo, M.J.
  • Queral, C.
  • Jimenez, G.
  • Gomez-Magan, J.
  • Meléndez, E.
  • Sanchez-Perea, M.

Abstract

The current main figure of merit for risk based decision making process based on Probabilistic Safety Assessment level 1 is usually related with the fuel failure (i.e., Peak Cladding Temperature (PCT)>1477.15K). In this approach, the core damage is the first and necessary step in a potential radiological release, being the containment failure the second one. Nevertheless, SGTR sequences in PWR plants are able to release large quantities of radioactive products without previous core damage or containment failure. For that reason, it seems necessary to analyze which sequences exceed the allowed offsite dose criteria prior to the core damage criterion.

Suggested Citation

  • Rebollo, M.J. & Queral, C. & Jimenez, G. & Gomez-Magan, J. & Meléndez, E. & Sanchez-Perea, M., 2016. "Evaluation of the offsite dose contribution to the global risk in a Steam Generator Tube Rupture scenario," Reliability Engineering and System Safety, Elsevier, vol. 147(C), pages 32-48.
    • Handle: RePEc:eee:reensy:v:147:y:2016:i:c:p:32-48
    DOI: 10.1016/j.ress.2015.10.016
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    3. Park, Jinkyun & Jung, Jae-Yoon & Heo, Gyunyoung & Kim, Yochan & Kim, Jaewhan & Cho, Jaehyun, 2018. "Application of a process mining technique to identifying information navigation characteristics of human operators working in a digital main control room – feasibility study," Reliability Engineering and System Safety, Elsevier, vol. 175(C), pages 38-50.
    4. Maidana, Renan G. & Parhizkar, Tarannom & Gomola, Alojz & Utne, Ingrid B. & Mosleh, Ali, 2023. "Supervised dynamic probabilistic risk assessment: Review and comparison of methods," Reliability Engineering and System Safety, Elsevier, vol. 230(C).
    5. Kotaro Kubo & Xiaoyu Zheng & Yoichi Tanaka & Hitoshi Tamaki & Tomoyuki Sugiyama & Sunghyon Jang & Takashi Takata & Akira Yamaguchi, 2023. "Simulation-based dynamic probabilistic risk assessment of an internal flooding-initiated accident in nuclear power plant using THALES2 and RAPID," Journal of Risk and Reliability, , vol. 237(5), pages 947-957, October.
    6. 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).

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