• 제목/요약/키워드: Radioactive waste repository

검색결과 322건 처리시간 0.023초

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.

Site Monitoring of LILRW Repository: Korean Case

  • Lee, H.;Im, C.B.;Noh, M.;Shim, T.M.;Choi, H.;Hyun, S.G.;Park, J.;Kim, S.Y.
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2009년도 학술논문요약집
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    • pp.506-507
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    • 2009
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Site Selection Process for Spent Fuel in Finland

  • Auvinen, Anssi;Lehtonen, Aleksis;Riekkola, Reijo
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2009년도 학술논문요약집
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    • pp.179-181
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    • 2009
  • This presentation is a short summary of the Finnish process for selection and characterisation of potential sites for geological deep disposal of spent nuclear fuel. The process lasted nearly two decades from 1983 to 2000, and was concluded by the Government's Decision in Principle (DiP) on the construction of a repository in Olkiluoto. This presentation gives an outline of the early site selection criteria and a description of this process.

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고준위폐기물처분장의 완충재 개념 도출: 접근방안 (Establishing the Concept of Buffer for a High-level Radioactive Waste Repository: An Approach)

  • 이재완;이민수;최희주
    • 방사성폐기물학회지
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    • 제13권4호
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    • pp.283-293
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    • 2015
  • 고준위폐기물처분장에서 완충재는 공학적방벽의 주요 구성요소 중 하나이다. 본 연구에서는 국 내외의 완충재 요구사항과 성능기준을 분석하고, 우리나라 고준위폐기물처분장에 적합한 완충재 개념 도출을 위한 접근방안을 제시하였다. 완충재의 주요 성능기준 인자항목으로, 수리전도도, 핵종 저지능, 팽윤압, 열전도도, 역학적 특성치(mechanical properties), 유기물함량(organic carbon content), 일라이트화 속도(illitization rate) 등을 고려하였다. 우리나라 고준위폐기물처분장 완충재 물질로서 국산 벤토나이트(Ca-벤토나이트)와 대안재로 MX-80 벤토나이트(Na-벤토나이트)를 제안하였다. 완충재의 기술사양은 Ca-벤토나이트 경우엔 우리나라의 성능기준을, Na-벤토나이트의 경우는 스웨덴의 성능기준을 보수적으로 만족하는 값으로 설정하였다. 완충재의 두께는 전단거동, 핵종 유출, 열전도의 측면에서 평가하여 결정하였으며, 평가결과 완충재의 두께는 0.25 ~ 0.5 m 사이가 적절하였다. 그러나 최종적인 완충재의 두께는 향후 보다 심도 있는 열-수리-역학적 평가와 경제적, 공학적 측면을 고려하여 결정하여야 할 것이다.

처분환경조건에서 모의 방사성폐기물 붕규산유리고화체의 장기침출률 (Long-term leach rates of simulated borosilicate waste glasses under a repository condition)

  • 전관식;김승수;최종원
    • 방사성폐기물학회지
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    • 제1권1호
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    • pp.41-46
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    • 2003
  • 심부 처분환경조건에서 붕규산유리고화체의 장기침출거동을 규명하기 위하여 3종의 모의붕규산유리고화체에 대한 장기침출실험이 1997년에 착수되었다. 5년간의 침출결과는 붕소가 본 붕규산유리고화체의 장기침출지표물질로 사용될 수 있음을 확인시켜 주었고, 비록 고화체들의 조성은 약간씩 다르지만, 초기 1년여 기간동안의 침출률을 제외한 장기침출률은 S/V에도 무관하게 0.03g/$m^2$-day 에 근접하는 경향을 보여주고 있다.

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방사성 폐기물의 열하중에 의한 절리암반의 거동에 관한 수치해석적 연구 (A Numerical Study on the Response of Jointed Rock Mass Due to Thermal Loading of Radioactive Waste)

  • 문현구;주광수
    • 터널과지하공간
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    • 제4권2호
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    • pp.102-118
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    • 1994
  • Thermomechanical analysis is conducted on the radioactive repository in deep rock mass considering the in-situ stress, excavation and thermal loading of a radioactive waste. Thermomechanical properties of a discontinuous rock mass are estimated by a theoretical method so called sequential analysis. Using the estimated properties as input for finite element analysis, the influence on temperature distribution and thermal stress is analyzed within the scope of 2-dimensional steady state and transient heat transfer and coupled thermal elastic plastic behaviour. Granitic rock mass is taken for this analysis. The analysis is done for two different rock mass conditions, i.e. continuous-homogeneous and highly jointed conditions, for the purpose of comparison. In the case of steady state, the extent of disturbed zone around the storage tunnel due to the heat production of the spent-fuel canister varies depending on the thermomechanical properties of the rock mass. In the case of transient analyses, the response of the jointed rock mass to the thermal loading after radioactive waste disposal varies significantly with time, resulting in dramatic changes in the both size and location of disturbed zone.

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