한국안전학회지 (Journal of the Korean Society of Safety)

  • 제35권5호
  • /
  • Pages.115-120
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  • 2020
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  • 1738-3803(pISSN)
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  • 2383-9953(eISSN)
한국안전학회 (The Korean Society of Safety)
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원자로 이용률 향상을 위한 냉중성자원 시설의 고장모드영향분석 및 정지이력의 원인분석

FMEA for CNS Facility and Cause Analysis of Shutdown Events to Improve Reactor Availability

  • 투고 : 2020.08.04
  • 심사 : 2020.09.21
  • 발행 : 2020.10.31
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초록

From 2009 when the CNS facility was installed, the number of reactor failures due to abnormal CNS facility system has increased significantly. Of the total of 19 nuclear reactor shutdowns over the six years from 2009 to 2019, there were 10 nuclear reactor shutdowns associated with the CNS facility, which are very numerous. Therefore, this report intends to analyze the history of nuclear reactor shutdowns due to CNS facility system failure in detail, and to present the root cause and solution to problems. As a result of FMEA implementation of CNS facility system, a total of 76 SPVs were selected. In addition, 10 cases of reactor shutdown history due to CNS facility system abnormalities were analyzed in detailed, and improvement plans for solving the root cause and problem were suggested for each trip history. The results of this study are expected to be able to operate the domestic research reactor and CNS facilities more stably by providing effective measures to prevent recurrence of CNS facilities and reactor trips.

키워드

참고문헌

  1. Y. H. Lee, "Analysis of Initiating Event Frequencies for PSA based on the Unexpected Reactor Trip Events at a Research Reactor", Spring Conference of the Korean Society of Safety 2020.
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  3. KAERI, Safety Analysis Report of HANARO, Chapter 11, Korea Atomic Energy Research Institute, 2020.
  4. S. Wu et al., "Development of Cold Neutron Research Facility and Utilization Technology", KAERI/RR-3158/2009, Korea Atomic Energy Research Institute, 2009.
  5. J. W. Hyun et al., "Failure Mode Effective Analysis for Selection of Single Point Vulnerability in New Type Nuclear Power Plant", Transaction of Korean Society of Pressure Vessel and Piping, Vol. 10, No. 1, pp. 31-36, 2014. https://doi.org/10.20466/KPVP.2014.10.1.031
  6. Y. H. Lee, "A Study on the Final Probabilistic Safety Assessment for the Jordan Research and Training Reactor," J. Korean Soc. Saf., Vol. 35, No. 3, pp. 86-95, 2020. https://doi.org/10.14346/jkosos.2020.35.3.86