• 제목/요약/키워드: Deep geological disposal of high-level radioactive waste

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해외국가별 고준위방사성폐기물 처분 후보부지 조사를 위한 기준 분석 (Comparative Analysis of Siting Criteria of High-Level Radioactive Waste Disposal in Leading Countries)

  • 나태유;채병곤;박의섭;김민준
    • 지질공학
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    • 제34권1호
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    • pp.117-136
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    • 2024
  • 고준위방사성폐기물 심층처분은 국가의 안전과 환경 보호를 위해 필수적이며, 각 나라의 지질학적, 사회적 환경에 적합한 부지선정기준의 확립은 이 과정에서 중요한 단계이다. 논문의 목적은 고준위방사성폐기물의 심층처분 부지를 확보하는 과정에서 국가별로 적용되는 다양한 지질학적 및 사회적 선정기준을 비교분석하는 것이다. 이 연구에서는 고준위방사성폐기물 처분 선도국들이 설정한 부지선정기준을 중심으로 비교분석을 수행하였으며, 각 국가별 선정기준 분석결과, 국가별 지질조건 및 환경을 반영한 선정기준을 차별적으로 설정하였음을 확인하였다. 연구의 결과는 우리나라의 고준위방사성폐기물 심층처분 부지선정기준 마련에 중요한 기반 자료로 활용될 수 있을 것이며, 국가의 지속 가능한 발전과 환경 보호에 이바지하게 될 것으로 기대된다.

The Swiss Radioactive Waste Management Program - Brief History, Status, and Outlook

  • Vomvoris, S.;Claudel, A.;Blechschmidt, I.;Muller, H.R.
    • Journal of Nuclear Fuel Cycle and Waste Technology
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    • 제1권1호
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    • pp.9-27
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    • 2013
  • Nagra was established in 1972 by the Swiss nuclear power plant operators and the Federal Government to implement permanent and safe disposal of all types of radioactive waste generated in Switzerland. The Swiss Nuclear Energy Act specifies that these shall be disposed of in deep geological repositories. A number of different geological formations and sites have been investigated to date and an extended database of geological characteristics as well as data and state-of-the-art methodologies required for the evaluation of the long-term safety of repository systems have been developed. The research, development, and demonstration activities are further supported by the two underground research facilities operating in Switzerland, the Grimsel Test Site and the Mont Terri Project, along with very active collaboration of Nagra with national and international partners. A new site selection process was approved by the Federal Government in 2008 and is ongoing. This process is driven by the long-term safety and feasibility of the geological repositories and is based on a step-wise decision-making approach with a strong participatory component from the affected communities and regions. In this paper a brief history and the current status of the Swiss radioactive waste management program are presented and special characteristics that may be useful beyond the Swiss program are highlighted and discussed.

A Current Status of Natural Analogues Programs in Nations Considering High-Level Radioactive Waste Disposal

  • HunSuk Im;Dawoon Jeong;Min-Hoon Baik;Ji-Hun Ryu
    • 방사성폐기물학회지
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    • 제21권1호
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    • pp.65-93
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    • 2023
  • Several countries have been operating radioactive waste disposal (RWD) programs to construct their own repositories and have used natural analogues (NA) studies directly or indirectly to ensure the reliability of the long-term safety of deep geological disposal (DGD) systems. A DGD system in Korea has been under development, and for this purpose a generic NA study is necessary. The Korea Atomic Energy Research Institute has just launched the first national NA R&D program in Korea to identify the role of NA studies and to support the safety case in the RWD program. In this article, we review some cases of NA studies carried out in advanced countries considering crystalline rocks as candidate host rocks for high-level radioactive waste disposal. We examine the differences among these case studies and their roles in reflecting each country's disposal repository design. The legal basis and roadmap for NA studies in each country are also described. However because the results of this analysis depend upon different environmental conditions, they can be only used as important data for establishing various research strategies to strengthen the NA study environment for domestic disposal system research in Korea.

High-efficiency deep geological repository system for spent nuclear fuel in Korea with optimized decay heat in a disposal canister and increased thermal limit of bentonite

  • Jongyoul Lee;Kwangil Kim;Inyoung Kim;Heejae Ju;Jongtae Jeong;Changsoo Lee;Jung-Woo Kim;Dongkeun Cho
    • Nuclear Engineering and Technology
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    • 제55권4호
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    • pp.1540-1554
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    • 2023
  • To use nuclear energy sustainably, spent nuclear fuel, classified as high-level radioactive waste and inevitably discharged after electricity generation by nuclear power plants, must be managed safely and isolated from the human environment. In Korea, the land area is limited and the amount of high-level radioactive waste, including spent nuclear fuels to be disposed, is relatively large. Thus, it is particularly necessary to maximize disposal efficiency. In this study, a high-efficiency deep geological repository concept was developed to enhance disposal efficiency. To this end, design strategies and requirements for a high-efficiency deep geological repository system were established, and engineered barrier modules with a disposal canister for pressurized water reactor (PWR)-type and pressurized heavy water reactor type Canada deuterium uranium (CANDU) plants were developed. Thermal and structural stability assessments were conducted for the repository system; it was confirmed that the system was suitable for the established strategies and requirements. In addition, the results of the nuclear safety assessment showed that the radiological safety of the new system met the Korean safety standards for disposal of high-level radioactive waste in terms of radiological dose. To evaluate disposal efficiency in terms of the disposal area, the layout of the developed disposal areas was assessed in terms of thermal limits. The estimated disposal areas were 2.51 km2 and 1.82 km2 (existing repository system: 4.57 km2) and the excavated host rock volumes were 2.7 Mm3 and 2.0 Mm3 (existing repository system: 4.5 Mm3) for thermal limits of 100 ℃ and 130 ℃, respectively. These results indicated that the area and the excavated volume of the new repository system were reduced by 40-60% compared to the existing repository system. In addition, methods to further improve the efficiency were derived for the disposal area for deep geological disposal of spent nuclear fuel. The results of this study are expected to be useful in establishing a national high-level radioactive waste management policy, and for the design of a commercial deep geological repository system for spent nuclear fuels.

The French Underground Research Laboratory in Bure: An Essential Tool for the Development and Preparation of the French Deep Geological Disposal Facility Cigéo

  • Pascal Claude LEVERD
    • 방사성폐기물학회지
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    • 제21권4호
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    • pp.489-502
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    • 2023
  • This article presents the crucial role played by the French underground research laboratory (URL) in initiating the deep geological repository project Cigéo. In January 2023, Andra finalized the license application for the initial construction of Cigéo. Depending on Government's decision, the construction of Cigéo may be authorized around 2027. Cigéo is the result of a National program, launched in 1991, aiming to safely manage high-level and intermediate level long-lived radioactive wastes. This National program is based on four principles: 1) excellent science and technical knowledge, 2) safety and security as primary goals for waste management, 3) high requirements for environment protection, 4) transparent and open-public exchanges preceding the democratic decisions and orientations by the Parliament. The research and development (R&D) activities carried out in the URL supported the design and the safety demonstration of the Cigéo project. Moreover, running the URL has provided an opportunity to gain practical experience with regard to the security of underground operations, assessment of environmental impacts, and involvement of the public in the preparation of decisions. The practices implemented have helped gradually build confidence in the Cigéo project.

고준위방사성폐기물 처분 Safety Case 개발을 통한 처분안전성 신뢰도 향상 (Confidence Improvement of Disposal Safety by Development of a Safety Case for High-Level Radioactive Waste Disposal)

  • 백민훈;고낙열;정종태;김경수
    • 방사성폐기물학회지
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    • 제14권4호
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    • pp.367-384
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    • 2016
  • 고준위방사성폐기물 심층처분에서 처분안전성의 신뢰도를 향상시킬 수 있는 방안으로 그리고 처분 프로그램 개발 및 인허가를 위해 많은 나라들에서 자국에 적합한 safety case를 개발하고 있다. 본 연구에서는 방사성폐기물 처분을 위한 safety case의 의의, 필요성, 개발과정들을 정리하고 소개하였다. 그리고 처분안전성을 safety case의 다양한 측면에서 논의하였다. 아울러 스위스, 일본, 미국, 스웨덴, 핀란드 등 해외의 safety case 개발 현황과 현재 KAERI에서 개발 중인 safety case의 개발 전략을 간략히 소개하였다. 고준위방사성폐기물 처분안전성의 신뢰도 향상을 위해 safety case 기반 하에서 어떤 노력들이 필요한지를 분석하였다. 그리고 국내 상황을 반영하여 신뢰할 수 있는 정보자료의 구축, 안전성 관련 과정들의 이해, 안전성평가의 불확실성 저감, 이해당사자와의 의사소통, 공정성과 투명성 확보 등의 실행 방안을 제안하고 논의하였다. 본 논문에 제시된 내용들은 심층처분 safety case를 이해하고, 국내에서 개발하고 있는 고준위방사성폐기물 처분 safety case 개발을 통한 처분안전성 신뢰도 향상에 기여할 수 있을 것으로 기대한다.

A Study on Thermal Load Management in a Deep Geological Repository for Efficient Disposal of High Level Radioactive Waste

  • Jongyoul Lee;Heuijoo Choi;Dongkeun Cho
    • 방사성폐기물학회지
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    • 제20권4호
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    • pp.469-488
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    • 2022
  • Technology for high-level-waste disposal employing a multibarrier concept using engineered and natural barrier in stable bedrock at 300-1,000 m depth is being commercialized as a safe, long-term isolation method for high-level waste, including spent nuclear fuel. Managing heat generated from waste is important for improving disposal efficiency; thus, research on efficient heat management is required. In this study, thermal management methods to maximize disposal efficiency in terms of the disposal area required were developed. They efficiently use the land in an environment, such as Korea, where the land area is small and the amount of waste is large. The thermal effects of engineered barriers and natural barriers in a high-level waste disposal repository were analyzed. The research status of thermal management for the main bedrocks of the repository, such as crystalline, clay, salt, and other rocks, were reviewed. Based on a characteristics analysis of various heat management approaches, the spent nuclear fuel cooling time, buffer bentonite thermal conductivity, and disposal container size were chosen as efficient heat management methods applicable in Korea. For each method, thermal analyses of the disposal repository were performed. Based on the results, the disposal efficiency was evaluated preliminarily. Necessary future research is suggested.

고준위방사성폐기물 심층처분을 위한 심부 시추공을 활용한 암반의 지구과학적 조사 (Geoscientific Research of Bedrock for HLW Geological Disposal using Deep Borehole)

  • 천대성;송원경;김유홍;최승범;이성곤;현성필;석희준
    • 터널과지하공간
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    • 제32권6호
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    • pp.435-450
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    • 2022
  • 고준위방사성폐기물 심층처분을 위한 단계별 부지선정에 있어 기본조사부터 심부 시추조사를 통해 부지선정에 필요한 요소들을 획득할 예정이다. 터널이나 유류지하저장소 등과 같은 암반구조물의 지반조사와 달리 고준위방사성폐기물 처분과 관련된 지반조사는 매우 깊은 심도까지 수행될 뿐 아니라 높은 수준의 품질관리가 요구된다. 본 보고에서는 심부 지질특성화에 필요한 요소를 획득하기 위해 수행하였던 750 m급 심부 시추경험을 토대로 심부 시추에 대한 방법론과 심부 시추 전, 시추 중, 시추 후 획득하는 지질학, 지구물리학, 수리화학, 수리지질학, 암반공학 등 다학제적 지구과학적 조사에 대한 절차 등에 대해 간략하게 서술하였다. 암반공학분야의 핵심 평가인자 중 현지응력에 대해서는 고준위방사성폐기물 심층처분관련 국외 사례와 국내 사례를 통하여 심도에 따른 응력변화를 고찰하였다.

Effect of Rock Mass Properties on Coupled Thermo-Hydro-Mechanical Responses at Near-Field Rock Mass in a Heater Test - A Benchmark Sensitivity Study of the Kamaishi Mine Experiment in Japan

  • Hwajung Yoo;Jeonghwan Yoon;Ki-Bok Min
    • 방사성폐기물학회지
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    • 제21권1호
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    • pp.23-41
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    • 2023
  • Coupled thermo-hydraulic-mechanical (THM) processes are essential for the long-term performance of deep geological disposal of high-level radioactive waste. In this study, a numerical sensitivity analysis was performed to analyze the effect of rock properties on THM responses after the execution of the heater test at the Kamaishi mine in Japan. The TOUGH-FLAC simulator was applied for the numerical simulation assuming a continuum model for coupled THM analysis. The rock properties included in the sensitivity study were the Young's modulus, permeability, thermal conductivity, and thermal expansion coefficients of crystalline rock, rock salt, and clay. The responses, i.e., temperature, water content, displacement, and stress, were measured at monitoring points in the buffer and near-field rock mass during the simulations. The thermal conductivity had an overarching impact on THM responses. The influence of Young's modulus was evident in the mechanical behavior, whereas that of permeability was noticed through the change in the temperature and water content. The difference in the THM responses of the three rock type models implies the importance of the appropriate characterization of rock mass properties with regard to the performance assessment of the deep geological disposal of high-level radioactive waste.

심부시추공 처분시스템의 국내적용 가능성 예비 평가 (Preliminary Evaluation of Domestic Applicability of Deep Borehole Disposal System)

  • 이종열;이민수;최희주;김경수;조동건
    • 방사성폐기물학회지
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    • 제16권4호
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    • pp.491-505
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    • 2018
  • 현재 기준개념으로 개발하여 상용화 단계에 있는 심층 동굴 처분기술에 대한 대안으로서 지질학적 조건이 더 안정적인 지하 3~5 km의 심도에 사용후핵연료를 포함한 고준위폐기물을 처분하는 심부시추공 처분기술의 국내 적용 가능성을 예비 평가 하였다. 이를 위하여 심부시추공 처분개념의 기술적 적용성 분석에 필요한 국내 기반암 분포특성 및 심부시추공 처분부지 적합성 평가 기술 분석과 대구경 심부시추기술을 평가하였다. 이들 분석결과를 바탕으로 심부시추공 처분시스템 설계 기준 및 요건에 적합한 심부시추공 처분용기 및 밀봉시스템 개념을 설정하여 예비 기준 심부시추공 처분 개념을 도출하였다. 그리고 도출된 예비 기준 처분시스템에 대하여 열적 안정성 및 그래픽 처분환경에서의 처분공정 모사 등 다양한 성능평가를 수행하고 이들을 종합하여 심부시추공 처분시스템의 국내 적용성에 대하여 다양한 관점에서의 예비평가를 수행하였다. 결론적으로, 심부시추공 처분시스템은 처분심도와 단순한 방법으로 인하여 안전성 및 경제적 타당성 측면에서 많은 장점이 있지만, 불확실성을 줄이고 인허가를 획득하기 위해서는 이 기술에 대한 현장실증이 필수적이다. 본 연구결과는 사용후핵연료 관리 국가정책 수립을 위한 공학적 근거자료로 활용이 가능하며, 심부시추공 처분기술에 관심을 갖는 방사성폐기물 관리 이해당사자들에게 필요한 정보자료로 제공될 수 있다.