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Fukushima Dai-Ichi Accident: Lessons Learned and Future Actions from the Risk Perspectives
양준언 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.1
The Fukushima Dai-Ichi accident in 2011 has affected various aspects of the nuclear society worldwide. The accidentrevealed some problems in the conventional approaches used to ensure the safety of nuclear installations. To prevent suchdisastrous accidents in the future, we have to learn from them and improve the conventional approaches in a more systematicmanner. In this paper, we will cover three issues. The first is to identify the key issues that affected the progress of theFukushima Dai-Ichi accident greatly. We examine the accident from a defense-in-depth point of view to identify such issues. The second is to develop a more systematic approach to enhance the safety of nuclear installations. We reexamine nuclearsafety from a risk point of view. We use the concepts of residual and unknown risks in classifying the risk space. All possibleaccident scenarios types are reviewed to clarify the characteristics of the identified issues. An approach is proposed to improveour conventional approaches used to ensure nuclear safety including the design of safety features and the safety assessmentsfrom a risk point of view. Finally, we address some issues to be improved in the conventional risk assessment andmanagement framework and/or practices to enhance nuclear safety.
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양준언 한국원자력학회 2012 Nuclear Engineering and Technology Vol.44 No.5
From the PSA point of view, the Fukushima accident of Japan in 2011 reveals some issues to be re-considered and/or improved in the PSA such as the limited scope of the PSA, site risk, etc. KAERI (Korea Atomic Energy Research Institute)has performed researches on the development of an integrated risk assessment framework related to some issues arisen after the Fukushima accident. This framework can cover the internal PSA model and external PSA models (fire, flooding, and seismic PSA models) in the full power and the low power-shutdown modes. This framework also integrates level 1, 2 and 3PSA to quantify the risk of nuclear facilities more efficiently and consistently. We expect that this framework will be helpful to resolve the issue regarding the limited scope of PSA and to reduce some inconsistencies that might exist between (1) the internal and external PSA, and (2) full power mode PSA and low power-shutdown PSA models. In addition, KAERI is starting researches related to the extreme external events, the risk assessment of spent fuel pool, and the site risk. These emerging issues will be incorporated into the integrated risk assessment framework. In this paper the integrated risk assessment framework and the research activities on the emerging issues are outlined.
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Multi-unit risk assessment of nuclear power plants: Current status and issues
양준언 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.8
After the Fukushima-Daiichi accident in 2011, the multi-unit risk, i.e., the risk due to several nuclearpower plants (NPPs) in a site has become an important issue in several countries such as Korea, Canada,and China. However, the multi-unit risk has been discussed for a long time in the nuclear communitybefore the Fukushima-Daiichi nuclear accident occurred. The regulatory authorities around the worldand the international organizations had proposed requirements or guidelines to reduce the multi-unitrisk. The concerns regarding the multi-unit risk can be summarized in the following three questions:How much the accident of an NPP in a site affects the safety of other NPPs in the same site?What is the total risk of a site with many NPPs?Will the risk of the simultaneous accidents at several NPPs in a site such as the Fukushima Daiichiaccident be low enough?The multi-unit risk assessment (MURA) in an integrated framework is a practical approach to obtainthe answers for the above questions. Even though there were few studies to assess the multi-unit riskbefore the Fukushima-Daiichi nuclear accident, there are still several issues to be resolved to perform thecomplete MURA. This article aims to provide an overview of the multi-unit risk issues and its assessment. We discuss the several critical issues in the current MURA to get useful insights regarding the multi-unitrisk with the current state art of probabilistic safety assessment (PSA) technologies. Also, the qualitativeanswers for the above questions are addressed.
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SAFETY ASSESSMENT OF KOREAN NUCLEAR FACILITIES: CURRENT STATUS AND FUTURE
백원필,양준언,하재주 한국원자력학회 2009 Nuclear Engineering and Technology Vol.41 No.4
This paper introduces the development of safety assessment technology in Korea, focusing on the activities of the Korea Atomic Energy Research Institute in the areas of system thermal hydraulics, severe accidents and probabilistic safety assessment. In the 1970s and 1980s, safety analysis codes and methodologies were introduced from the United States, France, Canada and other developed countries along with technology related to the construction and operation of nuclear power plants. The main focus was on understanding and utilizing computer codes that were sourced from abroad up to the early 1990s, when efforts to develop domestic safety analysis codes and methodologies became active. Remarkable achievements have been made over the last 15 years in the development and application of safety analysis technologies. In addition, significant experimental work has been performed to verify the safety characteristics of reactors and fuels as well as to support the development and validation of analysis methods.
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화재모델 CFAST를 이용한 원전 화재구역의 CCDP 평가(II)
이윤환,양준언,김운형,김종훈 한국화재소방학회 2005 한국화재소방학회논문지 Vol.19 No.3
This paper evaluates the fire safety level of eight pump rooms in the nuclear power plant using a fire model, CFAST. We estimate the Conditional Core Damage Probability (CCDP) of each room based on the analyzed results of CFAST. Eight rooms located on the primary auxiliary building of the nuclear power plant are high pressure safety injection pump room A/B, low pressure safety injection pump room A/B, containment spray pump room A/B, and motor-driven auxiliary feed water pump room A/B. The upper layer gas temperature of each room is estimated and the integrity of cable is reviewed. Based on the results, the integrity of the cable located at the upper part of compartment is maintained without thermal damage. The Conditional Core Damage Probability is reduced to half of the old values. Accordingly, the fire safety assessment for eight pump rooms using the fire model will be capable of reducing the uncertainty and to develop a more realistic model. 본 논문에서는 화재 모델 CFAST를 사용하여 원자력발전소에 있는 8개 펌프실의 화재 안전 수준을 평 가해 보고, 그 결과를 조건부 노심손상확률에 반영하여 분석해 보았다. 분석 대상 구역은 원자력발전소 일 차보조건물에 위치한 고압안전주입 펌프실 A/B, 저압안전주입 펌프실 A/B, 격납건물 살수 펌프실 A/B 및 모터구동 보조급수 펌프실 A/B 등 총 8곳이었다. 각 화재구역의 상부층 가스 온도를 분석하였으며, 분석 결과를 바탕으로 상부층에 위치한 케이블의 손상 유무를 파악하였다. 분석 결과에 의하면 총 8개 화 재구역의 상부층 케이블은 건전성을 유지하는 것으로 확인되었다. 케이블의 건전성 평가 결과를 바탕으로 각 화재구역의 조건부 노심손상확률을 평가한 결과, 기존의 보수적인 가정 하에 수행된 화재위험도분석 결 과보다 약 2배 정도 감소하는 보다 현실적이고 불확실성이 감소한 결과를 도출할 수 있었다.
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