• 제목/요약/키워드: Nuclear Power Plant decommissioning

검색결과 116건 처리시간 0.017초

Innovative Nuclear Power Plant Building Arrangement in Consideration of Decommissioning

  • Choi, Won-Jun;Roh, Myung-Sub;Kim, Chang-Lak
    • Nuclear Engineering and Technology
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    • 제49권3호
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    • pp.525-533
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    • 2017
  • A new concept termed the Innovative Nuclear Power Plant Building Arrangement (INBA) strategy is a new nuclear power plant building arrangement method which encompasses upfront consideration of more efficient decommissioning. Although existing decommissioning strategies such as immediate dismantling and differed dismantling has the advantage of either early site restoration or radioactive decommissioning waste reduction, the INBA strategy has the advantages of both strategies. In this research paper, the concept and the implementation method of the INBA strategy will be described. Two primary benefits will be further described: (1) early site restoration; and (2) radioactive waste reduction. Several other potential benefits will also be identified. For the estimation of economic benefit, the INBA strategy, with two primary benefits, will be compared with the immediate dismantling strategy. The effect of a short life cycle nuclear power plant in combination with the INBA strategy will be reviewed. Finally, some of the major impediments to the realization of this strategy will be discussed.

BIM을 활용한 원전 해체 물량산출 방안 (Plan of BIM-based Quantity Take-off for Nuclear Power Plant Decommissioning)

  • 정인수;원지선
    • 한국산학기술학회논문지
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    • 제16권9호
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    • pp.6297-6304
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    • 2015
  • 우리나라 최초의 원자력발전소인 고리 원전 1호기의 폐쇄가 결정됨에 따라 원전 해체가 화두가 되고 있다. 원전 해체는 우리나라에서 한번도 경험해 보지 못한 일로 해체 과정도 어렵고 시간도 많이 소요된다. 그 일부분인 해체물량 또한 파악이 어렵다. 본 연구에서는 최근 건설산업에 많이 활용되고 있는 BIM 기술을 원전 해체 물량산출에 활용할 수 있는 방안을 제시하였다. 그 결과, 원전 해체 공법선정 및 공정 확립, BIM 모델링 환경 준비, 작업분류체계 구축, 객체분류체계 구축, BIM 통합모델 작성, BIM 객체에 물량 속성 배분 등의 방안을 제시하였다. 제시한 방안은 영구정지 대상 원전이 집중적으로 발생하는 시기부터 유용하게 활용될 수 있다. 이에 기반한 기술확보를 통해 나아가 해외 원전 해체 사업 수주에도 유리하게 작용할 것으로 기대된다.

미국의 원전해체 비용평가 기초자료 및 동향 분석 (Status of Nuclear Power Plant Decommissioning Cost Analysis in USA)

  • 신상화;김순영
    • 한국방사선학회논문지
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    • 제12권2호
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    • pp.139-148
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    • 2018
  • 원전의 안전한 해체 관리를 위해 원전 해체 비용 평가는 매우 중요하다. 가장 많은 원전 해체 경험을 갖고 있는 미국의 경우 1970년대부터 원자력시설의 해체를 위하여 비용평가 연구를 진행하였다. 미국 NRC는 다양한 로형 및 원자력시설에 대한 해체 기술, 안전성 및 비용에 대한 연구를 수행하였다. 전체 해체 비용에서 운영허가종료비용이 가장 큰 비중을 차지하며, 그 다음으로는 사용후핵연료 관리, 부지복원순으로 평가되었다. 해체비용은 전체비용에 있어 운영허가종료가 제일 큰 비중을 차지하며 사용후핵연료관리, 부지복원 순으로 평가되었다. 즉시해체의 경우 지연해체에 비해 사용후핵연료관리 비용이 증가하였으며 지연해체의 경우 운영허가종료의 비용이 증가하였다. 전반적으로 즉시해체에 비해 지연해체의 경우가 뚜렷하게 이득이 보이지 않고 있다. 국내 원전 해체 비용 평가시 부지 조건에 따른 평가를 고려해야할 필요가 있다고 판단된다. 또한 국내의 경우 IAEA의 권고사항을 적용하여 방사성폐기물 분류체계를 재정비하였다. 이에 따라 해체시 발생하는 방사성폐기물 물량 산정시, 선행 미국 원전해체 자료를 신분류체계에 적합하게 활용하기 위한 방법을 개발해야할 필요가 있다. 특히 자체처분 대상폐기물 평가 방법론 설정은 해체비용의 정확성을 확보하는 중요한 인자로 작용할 것이다. 또한 국내 원전해체 비용 평가를 위하여 시설 특성과 작업 특성에 적용할 수 있는 정보자료 구축이 필요하다.

Calculation of preliminary site-specific DCGLs for nuclear power plant decommissioning using hybrid scenarios

  • Seo, Hyung-Woo;Sohn, Wook
    • Nuclear Engineering and Technology
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    • 제51권4호
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    • pp.1098-1108
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    • 2019
  • Korea's first commercial nuclear power plant at Kori site was permanently shut down in 2017 and is currently in transition stage. Preparatory activities for decommissioning such as historical site assessment, characterization, and dismantling design are being actively carried out for successful D&D (Dismantling and Decontamination) at Kori site. The ultimate goal of decommissioning will be to ensure the safety of workers and residents that may arise during the decommissioning of nuclear facilities and, thereby finally returning the site to its original status in accordance with the release criteria. Upon completion of decommissioning, the resident's safety at a site released will be assessed from the evaluation of dose caused by radionuclides expected to be present or detected at the site. Although the U.S. commercial nuclear power plants with decommissioning experience use different site release criteria, most of them are 0.25 mSv/y. In Korea, both the unrestricted and restricted release criteria have been set to 0.1 mSv/y by the Nuclear Safety and Security Commission. However, since the dose is difficult to measure, measurable concentration guideline levels for residual radionuclides that result in dose equivalent to the site release criteria should be derived. For this derivation, site reuse scenario, selection of potential radionuclides, and systematic methodology should be developed in planning stage of Kori site decommissioning. In this paper, for calculation of a preliminary site-specific Derived Concentration Guideline Levels (DCGLs) for the Nuclear Power Plant site, a novel approach has been developed which can fully reflect practical reuse plans of the Kori site by taking into account multiple site reuse scenarios sequentially, thereby striking a remarkable distinction with conventional approaches which considers only a single site scenario.

A study on characteristics and internal exposure evaluation of radioactive aerosols during pipe cutting in decommissioning of nuclear power plant

  • Kim, Sun Il;Lee, Hak Yun;Song, Jong Soon
    • Nuclear Engineering and Technology
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    • 제50권7호
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    • pp.1088-1098
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    • 2018
  • Kori unit #1, which is the first commercial nuclear power plant in Korea, was permanently shutdown in June 2017, and it is about to be decommissioned. Currently in Korea, researches on the decommissioning technology are actively conducted, but there are few researches on workers internal exposure to radioactive aerosol that is generated in the process of decommissioning nuclear power plants. As a result, the over-exposure of decommissioning workers is feared, and the optimal working time needs to be revised in consideration of radioactive aerosol. This study investigated the annual exposure limits of various countries, which can be used as an indicator in evaluating workers' internal exposure to radioactive aerosol during pipe cutting in the process of decommissioning nuclear power plants, and the growth and dynamics of aerosol. Also, to evaluate it, the authors compared/analyzed the cases of aerosol generated when activated pipes are cut in the process of nuclear power plants and the codes for evaluating internal exposure. The evaluation codes and analyzed data conform to ALARA, and they are believed to be used as an important indicator in deriving an optimal working time that does not excess the annual exposure limit.

Preliminary Analysis on Decommissioning Strategies for Fukushima Daiichi Nuclear Power Station From Waste Management Perspective

  • Watanabe, Naoko;Yanagihara, Satoshi
    • 방사성폐기물학회지
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    • 제19권3호
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    • pp.297-306
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    • 2021
  • In this study, basic strategies for the decommissioning and site remediation of the Fukushima Daiichi Nuclear Power Station (FDNPS) were investigated. Six scenarios were formulated based on two of the three decommissioning strategies of nuclear power plants defined by the International Atomic Energy Agency (IAEA): immediate dismantling and deferred dismantling. A multicriteria decision analysis was performed to analyze the preferences of the options from the viewpoints of the timeframe to complete decommissioning, the resulting waste, the site usability, and the availability of the radioactive waste disposal route. The same six scenarios were applied to both the FDNPS and the nuclear power plants that ceased operation after a normal plant life cycle for comparison. For the FDNPS, the decommissioning project involved fuel debris retrieval, dismantling, and site remediation. The analysis results suggest that the balance between the amount of waste and the time to achieve the end state may be one of the most critical factors to consider when planning the decommissioning and site remediation of the FDNPS.

A Study on the Radiological Emergency Plan for Decommissioning Nuclear Power Plant

  • Hye-Jin Son;Chang-Lak Kim
    • 방사성폐기물학회지
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    • 제22권1호
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    • pp.91-104
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    • 2024
  • Safe radiation management is essential not only for operational nuclear power plants but also for nuclear plants to be decommissioned. When spent nuclear fuel is present on-site, meticulous radiation emergency plans are necessary to ensure safety. In Korea, numerous radiation emergency plans have been established for operational nuclear reactors. These plans delineate distinct response mitigation measures for white, blue, and red emergencies. However, clear regulations are yet to be devised for radiation emergency plans for reactors to be decommission. Therefore, this study investigated the decommissioning plan and status of Kori unit 1 to comprehensively analyze the current status of decommissioning safety in Korea. In this study, radiation emergency plans of decommissioning nuclear power plants abroad were reviewed to confirm radiation emergency action levels. Furthermore, radioactive waste treatment facilities, to be used for decommissioning reactors in Korea were evaluated. Moreover, the study assessed emergency plans (especially, emergency initiating conditions) for operational nuclear power plants in Korea for potential use in the decommissioning phase. This study proposed an emergency initiating condition that can be used for decommissioning reactors in Korea. Considering the anticipated introduction of plasma torch melting facility in Korea, this study examined the conditions of radiation emergency plans can be altered. This study identified effective measures and guidelines for managing radiological emergency initiating conditions, and effective decommissioning of nuclear power plants in Korea.

국내 원전 해체시 방사선환경영향평가 방안 (Preparation of Radiological Environmental Impact Assessment for the Decommissioning of Nuclear Power Plant in Korea)

  • 이상호;서형우;김창락
    • 방사성폐기물학회지
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    • 제16권1호
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    • pp.107-122
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    • 2018
  • 국내 최초의 상업원전인 고리1호기가 2017년 6월에 영구 정지되었다. 고리1호기 해체를 시작으로 한국은 원전 해체시장에 본격적으로 발을 내딛는다. 원자력발전소 해체를 위해서는 고려해야 할 사항들이 많으며, 방사선환경영향평가 또한 그 중 하나이다. 방사선환경영향평가의 목적은 주변주민의 건강과 안전을 도모하기 위해, 해체 전 및 해체 중에 해당 시설에서 방출되는 방사성물질로부터 주변주민이 받는 피폭방사선량이 규제 제한치를 초과하지 않음을 확인하는 것이다. 현재 국내에는 해체시 방사선환경영향평가서를 작성하는데 필요한 세부지침이 미비한 상황으로, 다수의 원전 해체 경험을 보유한 미국의 해체시 방사선환경영향평가서를 비교 분석하여 국내 상황에 맞는 해체시 방사선환경영향평가 방안을 개발하였다.

Comparison of the DeSa Project and the Preliminary Decommissioning Plan for Shin-Kori Units 5 and 6 in Terms of Graded Approaches

  • Changju Song;Tae Young Kong;Seongjun Kim;Jinho Son;Woo Seok Choi;hwapyoung Kim;Jiung Kim;Hee Geun Kim
    • 방사선산업학회지
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    • 제17권2호
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    • pp.143-150
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    • 2023
  • A graded approach applies safety requirements differentially, depending on the risk potential. An advantage of applying a graded approach is that safety assessments can be conducted repeatedly by focusing on areas with relatively higher risk than on those with low risk when decommissioning a nuclear power plant (NPP). The International Atomic Energy Agency (IAEA) recommends applying a graded approach to decommissioning NPPs worldwide. In Korea, the definition of the graded approach requires to be clarified. This study compared the decommissioning method used in Korean NPPs with the IAEA graded approach and examined whether the graded approach can be applied to decommissioning NPPs in Korea. As a result of the comparison, the preliminary decommissioning plan for Shin-Kori Units 5 and 6 showed that the decommissioning method for Korean NPPs is similar to the five-step IAEA graded approach.

국내 원자로시설 해체계획서 세부 작성지침(안) 개발 (Development of the draft guidelines of the decommissioning plan for a nuclear power plant in Korea)

  • 이정민;문주현
    • 방사성폐기물학회지
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    • 제11권3호
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    • pp.213-227
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    • 2013
  • 원자로시설 해체계획서 작성은 원자로시설의 안전한 해체, 해체폐기물의 발생 최소화, 사람과 환경 보호 등을 위해 원자로시설 해체에 앞서 반드시 필요하다. 우리나라는 고리 1호기, 월성 1호기가 머지않은 시기에 해체를 맞이하게 되지만, 해체계획서를 작성하는데 필요한 관련 세부 지침이 미비한 상황이다. 이에 따라 본 논문에서는 IAEA의 원자력 국제 안전기준과 원자로시설 해체경험과 선진화된 규제체계를 보유하고 있는 미국, 영국, 프랑스의 해체계획서 작성 지침을 비교분석하고 국내 상황을 감안하여 원자로시설 해체계획서 세부 작성지침(안)을 개발하였다. 본 논문에서 개발한 작성지침(안)은 국내 원자로시설 해체 관련 법령을 정비하고 해체사업자가 원자로시설을 해체하고자 할 때 미리 준비사항을 알려주는 역할을 할 것으로 기대되고 있다.