• 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.

• 자원환경지질
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• 제28권3호
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• pp.279-286
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• 1995

The amount of the high level radioactive wastes in Korea will be increased up to 14,297 MTU about 2010 year. Most of countries adopt the concept of deep burial repository in high level radioactive waste disposal. Because the high level radioactive wastes are very toxic in biosphere and to human, the data verifing its never return to the biosphere are requisite for the disposal. Presently, the evaluating techniques for the high level radioactive waste disposal are not fully developed. Therefore, in order to dispose the high level radioactive wastes in proper time the R & D of it is urged in our country. The R & D and/or the international joint research programme for the disposal of high level wastes have already been proceeded. In our country no plan for its disposal has been prepared. It is the time that the direction of the R & D is to be discused seriously. The R & D for the disposal of high level radioactive wastes in Korea is believed to be focused on developing the pecular techniques such as in situ characteristics of groundwater flowage, and change of properties of in situ rock mass at thermal effects.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2010년도 춘계 학술발표회
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• pp.791-800
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• 2010

This paper presents the construction status and the conceptual designs of midium and high level radioactive waste disposal facilities from all around world. For the midium radioactive waste, a shallow disposal using trench or a deep depth disposal are adopted. However, these are rather focusing on the social and cultural point of view than the technical. Meanwhile, the high level radioactive waste is basically disposed in the deep underground. The corresponding ground conditions are usually dense and composed of sedimentary and crystalline rocks mainly with low permeability. A barrier system is made of canister which consists of copper, titanium, and tin. The inner and outer side of the canister are composed of different materials respectively.

• 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.

• Nuclear Engineering and Technology
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• 제45권1호
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• pp.29-40
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• 2013

Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for spent fuel) for PWR and CANDU spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR spent fuels and 16,000 MtU of CANDU spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR spent fuel since 2007. However, since no decision was made for the CANDU spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.

• 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.

• 방사성폐기물학회지
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• 제10권1호
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• pp.55-62
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• 2012

고준위폐기물 처분과 관련하여, 최근 저장소 형태의 처분장 개념에 대한 대안으로 검토되고 있는 시추공 처분 개념에 대한 연구 현황을 정리하고 시추공 처분 개념의 국내 적용 가능성과 필요한 연구 항목에 대해 논의하였다. 현재 미국과 스웨덴을 중심으로 논의된 시추공 처분 개념은 심부시추공을 설치하여 지하 3 - 5km 구간에 고준위폐기물을 처분하는 것을 의미하며, 현재까지의 연구 결과에 의하면 이 처분 개념은 심부지하수의 층상구조, 작은 규모의 지표시설 등으로 인해 처분 및 비용 효율이 클 것으로 예상된다. 이에 반해 국내에는 축적된 심부 지질 자료가 없어 적용 가능성에 대한 논의할 여지가 없다. 이에 저장소 형태의 처분장 개념에 대한 대안으로 시추공 처분 개념을 검토하기 위해서는 향후 심지층 자료 확보, 공학적 방벽 연구, 수치모의모델 개발, 처분 기술 개발 등의 연구가 필요하다.

• 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.

• 방사성폐기물학회지
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• 제9권2호
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• pp.87-92
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• 2011

본 논문은 극저준위폐기물 관리에 관한 중국의 정책과 규정들을 소개하고 있다. 오래된 시설의 중요한 해체 및 부지복구 프로그램에 주어진 바와 같이, 극저준위폐기물의 처분을 위한 새로운 시설의 필요성이 대두되고 있다. 여러가지 일반적인 설계원리들은 다중방벽에 의해 폐기물을 격리시키는 중저준위폐기물 처분시설과 같다. 콘크리트 방벽을 사용하는 것 대신에 벤토나이트 또는 고밀도 폴리에틸렌 멤브레인을 사용하는 것 외에 통상적으로 처분시설의 설계는 위해폐기물 처분시설의 설계와 같다 극저준위폐기물 처분시설 2개소의 공학적 설계가 소개되었다.

• Nuclear Engineering and Technology
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• 제40권5호
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• pp.429-438
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• 2008

The objective of the present study is the depth and layout optimizations of a single layer, high level radioactive waste repository in a discontinuous rock mass with special joint set arrangements. A single layer repository model, considering variations in the repository depths, pitches, and tunnel spacings, is used to analyze the thermomechanical interaction behavior. It is assumed that the repository is constructed in saturated granite with joints; the PWR spent fuel in a disposal canister is installed in a deposition drift which is then sealed with compacted bentonite; and the backfill material is filled in the repository tunnel. The decay heat generated by the high level radioactive wastes governs the thermomechanical behavior of the near field rock mass of the repository. The temperature and displacement behavior of the repository is influenced more by the pitch variations than the tunnel spacing and repository depth. However, the stress behavior is influenced more by the repository depth variations than the pitch and tunnel spacing. For the final selection of the tunnel spacing, pitch, and repository depth, other aspects such as the nuclide migration through a groundwater flow path, construction costs, operation costs, and so on should be considered.