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원자력발전소 해체 위험도 평가 방법론 개발
Suggestion of Risk Assessment Methodology for Decommissioning of Nuclear Power Plant 원문보기

Journal of nuclear fuel cycle and waste technology = 방사성폐기물학회지, v.17 no.1, 2019년, pp.95 - 106  

박병익 (한국전력국제원자력대학원대학교) ,  김주열 (한국전력국제원자력대학원대학교) ,  김창락 (한국전력국제원자력대학원대학교)

초록
AI-Helper 아이콘AI-Helper

원전 해체를 준비함에 있어 정성적 또는 정량적 위험도 평가는 필수요소이다. 해체 공정간 발생하는 방사선학적 및 비방사선학적 위험요소는 해체 작업자 및 대중의 안전을 보장하기 위해 사전에 평가되어야 한다. 현재 해체 경험이 많은 미국의 기존 사업자들 및 NRC의 경우 위험의 중대성만 평가하는 결정론적 위험도 평가에 집중하고 있다. 하지만 최근 IAEA는 위험도 매트릭스를 활용한 위험도평가를 결정론적 위험도 평가의 대체안으로 제안하고 있다. 따라서 본 연구에서는 위험도평가에 앞서 해체 공정 별 해체 활동을 Risk Breakdown Structure에 맞추어 정리하였고, 미국 20여개 해체 원전에서 해체 공정별 위험도 평가 시행 중 선정한 해체 활동간 잠재적 사고를 해체 활동에 맞게 체계적으로 정리하였다. 그리고 복합 리스크 매트릭스를 개발 및 활용하여 해체 공정간 방사선학적 및 비방사선학적 위험요소의 위험도를 평가하여 정량적으로 수치화 하였다.

Abstract ▼ AI-Helper 아이콘AI-Helper

The decommissioning of nuclear power plants should be prepared by quantitative and qualitative risk assessment. Radiological and non-radiological hazards arising during decommissioning activities must be assessed to ensure the safety of decommissioning workers and the public. Decommissioning experie...

주제어

#원전 해체   #위험도평가   #위험도 매트릭스   #잠재적 사고   #위험요소  

AI 본문요약
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* AI 자동 식별 결과로 적합하지 않은 문장이 있을 수 있으니, 이용에 유의하시기 바랍니다.

제안 방법

  • In this study, the risk factors in risk assessments for decommissioning of Nuclear Power Plant, which factors necessary to perform risk assessments, is identified and studied to suggest the risk assessment methodology. The study was based on risk assessment method of Korean Occupational Safety and Health Agency (KOSHA) using the data collected from U.
  • 77, but there are not many documents explaining in detail how risk matrix should be adopted to the actual risk assessment for decommissioning of NPPs. In this study, we have developed the risk matrix based on risk assessment guidelines from KOSHA, using criteria acquired from IAEA, DOE, and KOSHA. Using this matrix risk assessment methodology for decommissioning of NPP is suggested.
  • 77 [4]. This document focuses on deterministic approach, which mainly considers consequences of risk, to assess the risk in decommissioning activities. IAEA also suggests the risk matrix technique as the alternative to deterministic approach.

대상 데이터

  • The identification of hazards for individual activities is performed in this step. However, in this study, the potential accidents that were considered by twenty of U.S. decommissioned plants were identified as hazards. These accidents are possible NRC has utilized their research efforts, industry-related documents, and licensing-basis documents such as post-shutdown decommissioning activity reports (PSDARs), final safety analysis reports (FSARs), environmental assessments (EAs), or environmental impact statements (EISs) to obtain a list of potential accidents and their consequences from twenty of U.

이론/모형

  • The composite risk matrix was developed using developed criteria and level of likelihood used in KOSHA. All risks of the potential accidents already categorized were estimated using risk matrix all offsite dose exposure calculation result were acquired through NUREG Guide, PSDAR, EIS of decommissioned NPPs. The risk estimation showed that most of the risk of potential accidents were classified under risk class Ⅳ and smaller as it goes to risk classⅠ.
  • 1. Step risk factor analysis referenced from risk assessment methodology from KOSHA.
  • The risk assessment was performed on the potential accidents considered by U.S decommissioned NPP operators, on basis of the developed risk matrix and KOSHA risk assessment methodology. All of the decommissioning activities were recategorized under each decommissioning process and related potential accidents were reorganized under each decommissioning activities.
  • In this study, the risk factors in risk assessments for decommissioning of Nuclear Power Plant, which factors necessary to perform risk assessments, is identified and studied to suggest the risk assessment methodology. The study was based on risk assessment method of Korean Occupational Safety and Health Agency (KOSHA) using the data collected from U.S. Nuclear Regulatory Commission (NRC) and International Atomic Energy Agency (IAEA). The decommissioning activities organized in chronical order under stepwise process and related potential accidents of the activities are identified and classified.
본문요약 정보가 도움이 되었나요?

참고문헌 (13)

  1. International Atomic Energy Agency, Decommissioning of Facilities Using Radioactive Material, IAEA Safety Standards Series No. WS-R-5, IAEA, Vienna (2006). 

  2. K.S. Jeong, K.W. Lee, and H.K. Lim, "Risk Assessment on Hazards for Decommissioning Safety of a Nuclear Facility", Ann. Nucl. Energy, 37(12), 1751-1762 (2010). 

    상세보기 crossref

  3. K.S. Jeong, B.S. Choi, J.K. Moon, D.J. Hyun, J.H. Lee, G.H. Kim, H.S. Hwang, S.Y. Jeong, and J.J. Lee, "Risk Reduction Approach to Decommissioing Hazards of Nuclear Facilities", Ann. Nucl. Energy, 63, 382-386 (2014). 

    상세보기 crossref

  4. U.S. Department of Energy, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports, U.S. DOE, DOE-STD-1027-92, Washington, D.C. (1997). 

  5. International Atomic Energy Agency, Safety Reports Series No. 77, Safety Assessment for Decommissioning, IAEA, Vienna (2013). 

  6. Korean Occupational Safety and Health Agency, Guidelines for risk assessment of machinery and equipment manufacturing, G-51-2012, KOSHA (2012). 

  7. U.S. Nuclear Regulatory Commission, Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, U.S. NRC, NUREG-0586, Washington, D.C. (2002). 

  8. International Atomic Energy Agency, Safety Reports Series No. 77, Safety assessment for Decommissioning Annex 1, Part A Safety Assessment for Decommissioning of a Nuclear Power Plant, IAEA, Vienna (2013). 

  9. U.S. Department of Energy, Radiation protection for occupational Workers, U.S. DOE Order 5480.11, Washington, D.C. (1992). 

  10. Korean Occupational Safety and Health Agency, Risk Assessment Hand book, KOSHA (2015). 

  11. U.S. Nuclear Regulatory Commission, Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Platns Reports, U.S. NRC, NUREG-1738, Washington, D.C. (2001). 

  12. J.R. Travis, E.R. Davis, J.E. Grove, and A.M. Azarm, A Safety and Regulatory Assessment of Generic BWR and PWR Permanently Shutdown Nuclear Power Plants, U.S. NRC, NUREG/CR-6451, Washington, D.C. (1997). 

  13. IAEA and OECD/NEA, The International Nuclear Event Scale (INES) User's Manual, IAEA, Vienna (2001). 

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