• Title/Summary/Keyword: 방사성 폐기물 지층처분장

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Ventilation System Strategy for a Prospective Korean Radioactive Waste Repository (한국형 방사성 폐기물 처분장을 위한 환기시스뎀 전략)

  • Kim Jin;Kwon Sang-Ki
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.2
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    • pp.135-148
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    • 2005
  • In the stage of conceptual design for the construction and operation of the geologic repository for radioactive wastes, it is important to consider a repository ventilation system which serves the repository working environment, hygiene & safety of the public at large, and will allow safe maintenance like moisture content elimination in repository for the duration of the repositories life, construction/operation/closure, also allowing safe waste transportation and emplacement. This paper describes the possible ventilation system design criteria and requirements for the prospective Korean radioactive waste repositories with emphasis on the underground rock cavity disposal method in the both cases of low & medium-level and high-level wastes. It was found that the most important concept is separate ventilation systems for the construction (development) and waste emplacement (storage) activities. In addition, ventilation network system modeling, natural ventilation, ventilation monitoring systems & real time ventilation simulation, and fire simulation & emergency system in the repository are briefly discussed.

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Mechanical evolution of radioactive waste repository and rock mass - A review on ANDRA's case - (방사성 폐기물 지층 처분장과 암반의 역학적 특성 변화 - ANDRA의 예 -)

  • Chung, So-Keul;Synn, Joong-Ho
    • Tunnel and Underground Space
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    • v.18 no.3
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    • pp.165-174
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    • 2008
  • Thermo-hydro-chemico-mechanical evolution of the radioactive waste repository and surrounding geological media is one of the key issues for the radioactive waste disposal. This article describes not only the basic context for the site selection but also a reasonable strategy for the repository related research based on the results of the French repository project carried out by ANDRA (National radioactive waste management agency). To have some alternatives for the determination of a preferable depth and geological media, it would be recommendable to establish a database system. The curing process of the fractures or microfissures in the EDZ (Excavation Disturbed Zone) during operation time has to be examined considering the evolution of the EDZ and the reversibility of the repository. It is prerequisite to carry out a feasibility study and to validate the design concept and design parameters in a properly constructed underground research laboratory (URL) in Korea.

Introduction to Current Status and Researches for Rock Engineering of Finnish Geological Disposal of Spent Fuel (핀란드의 사용후핵연료 지층처분 현황 및 암반공학 관련 연구소개)

  • Hong, Suyeon;Kwon, Saeha;Min, Ki-Bok;Park, Eui-Seob
    • Tunnel and Underground Space
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    • v.29 no.4
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    • pp.215-229
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    • 2019
  • This technical note describes the current status of Finnish radioactive waste disposal project which started to construct the repository for spent nuclear waste for the first time in the world. Finland started operating nuclear power plant in 1977 and is currently operating four nuclear power plants. After detailed site surveys started in 1993, Olkiluoto was finally selected by the parliament of Finland as the site for geological disposal in 2001 followed by a construction license in 2015. If the operating license is approved by the government in the 2020s, it would be the world's first case of geological disposal. In ONKALO, a site-specific underground research facility at the site of Olkiluoto, various studies were conducted to verify the safety of the repository. Finland uses the KBS-3 disposal concept, and Korea considers a similar disposal concept because of similar rock formations. The entire process in Finland including the operation status of intermediate and low-level waste disposal, site investigation and selection stages, and the latest rock mechanics and hydrogeological studies in ONKALO are presented. Suggestions for the radioactive waste disposal in Korea is given based on the Finnish case.

Effect of Deformation Zones on the State of In Situ Stress at a Candidate Site of Geological Repository of Nuclear Waste in Sweden (스웨덴 방사성 폐기물 처분장 후보부지의 사례를 통해 살펴본 대규모 변형대가 암반의 초기응력에 미치는 영향)

  • Min, Ki-Bok
    • Tunnel and Underground Space
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    • v.18 no.2
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    • pp.134-148
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    • 2008
  • The state of in situ stress is an important factor in considering the suitability of a site as a geological repository for nuclear waste. In this study, three-dimensional distinct numerical analysis was conducted to investigate the effect of deformation zones on the state of stress in the Oskarshamn area, which is one of two candidate sites in Sweden. A discontinuum numerical model was constructed by explicitly representing the numerous deformation zones identified from site investigation and far-field tectonic stress was applied in the constructed model. The numerical model successfully captured the variation of measured stress often observed in the rock mass containing large-scale fractures, which shows that numerical analysis can be an effective tool in improving the understanding of the state of stresses. Discrepancies between measured and modelled stress are attributed to the inconsistent quality of measured stress, uncertainty in geological geometry. and input data for fractures.

Preliminary Study on the Jinju Formation in the Gyeongsang Basin to Evaluate Host Rock for High-level Radioactive Waste Geological Disposal: Focusing on Lithological and Mineralogical Characteristics (고준위방사성폐기물 지층처분 암종 평가를 위한 경상분지 진주층 예비연구: 암상 및 광물학적 특성을 중심으로)

  • Sung Kyung Hong;Kwangmin Jin
    • Economic and Environmental Geology
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    • v.57 no.4
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    • pp.387-396
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    • 2024
  • The geological disposal of high-level radioactive waste (HLW) involves permanently isolating the wastes in stable geological formations deep underground. Mudstone (siltstone and claystone) containing abundant clay minerals is proposed as a host rock for geological disposal of HLW because clay minerals have low permeability and high ion sorption/exchange capacity. Despite the widespread occurrence of sedimentary basins in Korea, there is a lack of evaluation of mudstone as host rocks for geological disposal. In this study, we utilized the JBH-1 borehole (7-754 m) obtained from the Jinju Formation to investigate the distribution trend and mineral compositions of mudstone. Additionally, we conducted comparative analyses with the Opalinus Clay in Switzerland considered as host rock of geological disposal of HLW. Claystone containing more than 40% clay minerals exhibit thick layers primarily in the upper section (7-350 m) of the JBH-1 borehole. While the clay minerals content of claystone does not show significant variation with depth, there are differences in the characteristics of feldspar and carbonate minerals. These mineralogical variations can led change in pore water chemistry and rock mechanical properties. The clay minerals content of claystone in the Jinju Formation is similar to that of the Opalinus Clay. However, there are notable differences in clay minerals composition. While the Opalinus Clay contains smectite-illite mixed-layer minerals, the Jinju Formation are dominated by illite indicating higher burial temperatures. This information will be useful for studying the host rock of HLW geological disposal site in Korea.

Putting nuclear waste to rest (해외 정보 - 영국의 고준위폐기물 영구 처분 계획)

  • 한국원자력산업회의
    • Nuclear industry
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    • v.36 no.5
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    • pp.61-66
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    • 2016
  • 영국은 약 3년에 걸친 공론화 과정을 통해 고준위 방사성폐기물을 가장 안전하게 관리할 수 있는 방안으로 지층 처분 방식을 선택하여 국가 정책으로 결정했다. 그러나 실제로 처분장이 건설되어 운영되기까지는 앞으로도 수십 년이라는 오랜 시간이 걸릴 것으로 예상되고 있다.

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저준위 방사성폐기물 동굴처분 안전성 평가 대상 시나리오 도출 및 확률론적 지하수 유동 평가 방법론 개발

  • Hwang, Yong-Su;Seo, Eun-Jin;Gang, Cheol-Hyeong
    • Proceedings of the Korean Society for Rock Mechanics Conference
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    • 2004.04a
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    • pp.123-140
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    • 2004
  • 저준위 방사성폐기물 안전성 평가를 위해서 안전성 평가 대상에 관한 기술이 이해당사자들이 이해하기 명확하고 쉽게 설정되어야 한다. 방사선적 안전성 평가 시나리오란 처분장으로부터 유출된 방사성 물질들이 공학적 방벽과 천연 방벽을 거쳐 생태계로 어떻게 이동하는가에 대한 설명으로 안전성 평가를 위한 일종의 대본과 같은 역할을 한다. 본 논문에서는 핵종 이동 현상을 RES(Rock Engineering System) 방법론에 의거 기술하였다. 국내 처분장의 특성을 고려하여 처분 시설은 연안에 동굴 처분 방식으로 건설된다고 가정하여 생태계를 산정하고, 공학적 및 천연 방벽들이 처분장 설계 시 예상한 기능들을 수행한다고 가정하여, 기준 시나리오를 설정하였다. 또한 다양한 설계 고려 요소들을 고려하여 대안 시나리오들을 도출하고자 하였다. 도출된 시나리오의 주요 항목들을 평가하기 위해서 AMF(Assessment Method Flowchart)를 도출하였다. 주어진 지형 조건에 따라 확률론적 방사선적 안전성 평가를 위해 각 지층 구조별 이동 거리 및 시간을 CONNECTFLOW를 이용해 산정하고, 그 결과들을 Response surface method를 이용해 확률 밀도함수로 도출하여 방사선적 안전성 종합 평가 코드인 MASCOT-K의 입력 자료로 활용되도록 하였다.

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Borehole Disposal Concept: A Proposed Option for Disposal of Spent Sealed Radioactive Sources in Tanzania (보어홀 처분 개념: 탄자니아의 폐밀봉선원 처분을 위한 제안)

  • Salehe, Mikidadi;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.11 no.4
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    • pp.293-301
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    • 2013
  • Borehole Disposal Concept (BDC) was initiated by the South African Nuclear Energy Corporation (NECSA) with the view to improve the radioactive waste management practices in Africa. At a time when geological disposal of radioactive waste is being considered, the need to protect ground water from possible radioactive contamination and the investigation of radionuclides migration through soil and rocks of zone of aeration into ground water has becomes very imperative. This is why the Borehole Disposal Concept (BDC) is being suggested to address the problem. The concept involves the conditioning and emplacement of disused sealed radioactive sources in an engineered facility of a relatively narrow diameter borehole (260 mm). Tanzania is operating a Radioactive Waste Management Facility where a number of spent sealed radioactive sources with long and short half lives are stored. The activity of spent sealed radioactive sources range from (1E-6 to 8.8E+3 Ci). However, the long term disposal solution is still a problem. This study therefore proposing the country to adopt the BDC, since the repository requires limited land area and has a low probability of human intrusion due to the small footprint of the borehole.

Review of Site Characterization Methodology for Deep Geological Disposal of Radioactive Waste (방사성폐기물의 심층 처분을 위한 부지특성조사 방법론 해외 사례 연구)

  • Park, Kyung-Woo;Kim, Kyung-Su;Koh, Yong-Kwon;Jo, Yeonguk;Ji, Sung-Hoon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.15 no.3
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    • pp.239-256
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    • 2017
  • In the process of site selection for a radioactive waste disposal, site characterization must be carried out to obtain input parameters to assess the safety and feasibility of deep geological repository. In this paper, methodologies of site characterization for radioactive waste disposal in Korea were suggested based on foreign cases of site characterization. The IAEA recommends that site characterization for radioactive waste disposal should be performed through stepwise processes, in which the site characterization period is divided into preliminary and detailed stages, in sequence. This methodology was followed by several foreign countries for their geological disposal programs. General properties related to geological environments were obtained at the preliminary site characterization stage; more detailed site characteristics were investigated during the detailed site characterization stage. The results of investigation of geology, hydro-geology, geochemistry, rock mechanics, solute transport and thermal properties at a site have to be combined and constructed in the form of a site descriptive model. Based on this site descriptive model, the site characteristics can be evaluated to assess suitability of site for radioactive waste disposal. According to foreign site characterization cases, 7 or 8 years are expected to be needed for site characterization; however, the time required may increase if the no proper national strategy is provided.