• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.791-792
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.227-228
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• 2005

• 방사성폐기물학회지
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• 제10권3호
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• pp.133-141
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• 2012

고준위 방사성폐기물 처분에 대한 종합 성능 평가를 위해 처분장 성능 및 안전성에 미치는 영향들을 단위 현상, 사건, 공정 (FEP)으로 분류하고 이들을 발생 가능성, 결과 영향, 규제, 특정 부지의 적합성 등을 고려하여 중요도를 평가한 후 유사한 FEP들을 그룹화하여 이들 FEP 그룹들 간의 상호 반응을 이해하고 이로부터 처분장으로부터 최종 생태계에 이르는 방사성 핵종들이 이동을 기술하는 시나리오를 도출하는 연구가 필요하다. 한국원자력연구원에서는 외국의 사례를 심층 분석하고 국내 전문가 의견 등을 종합하여 국내 처분 환경에 적합한 FEP들을 380 여개 포함하는 KAERI FEP List를 개발하였다. RES와 PID방법을 사용하여 처분장 방사선적 종합 안전성 평가에서 고려해야 될 5 가지 시나리오들을 도출하였다. 또한 고준위폐기물 처분안전성평가를 종합 데이터베이스 관리시스템인 KAERI CYPRUS를 개발하고 이들 결과물을 CYPRUS 내에 구축하였다.

• Nuclear Engineering and Technology
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• 제34권4호
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• pp.406-414
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• 2002

In TSPA of long-term post closure radiological safety on permanent disposal of HLW in Korea, appropriate management of input and output data through QA is necessary. The robust QA system is developed using the T2R3 principles applicable for five major steps in R&D＇s. The proposed system is implemented in the web-based system so that all participants in TSPA are able to access the system. In addition, the internet based input database for TSPA is developed. Currently data from literature surveys, domestic laboratory and field experiments as well as expert elicitation are applied for TSPA.

• Journal of Radiation Protection and Research
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• 제26권2호
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• pp.119-132
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• 2001

본 연구에서는 IAEA, OECD/NEA, ICRP등과 같은 국제기구에서 제안하는 권고기준과 고준위폐기물 처분사업을 계획하고 있는 국가의 관련기준을 비교 분석하여 현재 우리가 추구하고 있는 '고준위폐기물 기준 처분개념 설정'을 위한 안전 및 기술기준으로 도출하였다. 이 기준은 처분 안전성을 위한 일반 원칙과 기준 그리고 처분시스템의 성능요건 등으로 구분하여 작성하였다. 본 연구에서 제시된 기준들은 향후 예상되는 국가적인 기준이나 규제사항 개발에 좋은 참고자료로 사용될 수 있을 것이다. 또한 이들은 향후 국내의 심부 지질환경에 대한 특성조사 및 안전성 분석 등을 통하여 얻어지는 자료를 근거로 계속 수정될 것이다. 고준위폐기물 처분시스템의 개발 경험이 없는 우리 실정에서는 외국의 처분시스템 개발과 인허가 및 기술적 요건들의 변화과정과 원인 등을 주시하면서 우리 환경에 맞는 독자적 기술기준을 개발해 나가는 자세가 지속되어야 할 것이다.

• 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.

• Nuclear Engineering and Technology
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• 제31권6호
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• pp.83-100
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• 1999

As disposal packaging concepts of spent fuels generated from the domestic NPP, two types, one is to package PWR and CANDU spent fuels in different containers and the other is to package them together, were proposed. The configuration of the containers and the layout of underground repository, such as the container spacing and the deposition tunnel spacing, were developed. The layout of underground repository satisfies the thermal constraint of the bentonite buffer surrounding disposal container, which should be lower than $100^{\circ}C$ in order to keep the physical and chemical properties of bentonite From the spent fuel packaging concepts and container emplacement methods, seven options were developed. With a typical pair-wise comparison methods, AHP, the most promising disposal concept was selected based on the technology Point of view.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.51-59
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• 2004

The geological research as a part of HLW disposal program in Korea is carried out to provide necessary data for the establishment of the reference repository system in term of design and safety assessment in the crystalline rock terrains. Six deep boreholes were drilled to obtain hydrogeological and hydrochemical data from Jurassic granites in the Yuseong area, Korea. The core observation, televiewer logging and hydraulic testing were carried out during and after drilling and multi-packer system were installed in the boreholes of 500m depth for hydraulic and hydrochemical monitoring including environmental isotopes. The integration of hydrogeochemical and hydrodynamic data would be built greater confidence for the understanding of groundwater system in fractured rock mass. This geoscientific program could be possible to suggest a general guideline to develop the reference disposal concept of high-level radioactive waste in Korea.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4005-4012
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• 2022

As high-level radioactive waste (HLW) generated from nuclear power plants is harmful to the human body, it must be safely disposed of by an engineered barrier system consisting of disposal canisters and buffer and backfill materials. A gap exists between the canister and buffer material in a HLW repository and between the buffer material and natural rock-this gap may reduce the water-blocking ability and heat transfer efficiency of the engineered barrier materials. Herein, the basic characteristics and thermal properties of granular bentonite, a candidate gap-filling material, were investigated, and their effects on the temperature change of the buffer material were analyzed numerically. Heat transfer by air conduction and convection in the gap were considered simultaneously. Moreover, by applying the Korean reference disposal system, changes in the properties of the buffer material were derived, and the basic design of the engineered barrier system was presented according to the gap filling material (GFM). The findings showed that a GFM with high initial thermal conductivity must be filled in the space between the buffer material and rock. Moreover, the target dry density of the buffer material varied according to the initial wet density, specific gravity, and water content values of the GFM.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.755-756
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• 2004