• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.3
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• pp.183-192
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• 2005

Natural ventilation in radioactive waste repositories is considered to be less efficient than mechanically forced ventilation for the repository working environment and hygiene & safety of the public at large, for example, controlling the exposure of airborne radioactive particulate matter. It is, however, considered to play an important role and may be fairly efficient for maintaining environmental conditions of the repository over the duration of its lifetime, for example, moisture content and radon (Rn) gas elimination in repository. This paper describes the feasibility of using natural ventilation which can be generated in the repository itself, depending on the conditions of the natural environment during the periods of repository construction and operation. Evidences from natural cave analogues, actual measurements of natural ventilation pressures in mountain traffic tunnels with vertical shafts, and calculations of airflow rates with given natural ventilation pressures indicate possible benefits from passive ventilation for the prospective Korean radioactive waste repository. Natural ventilation may provide engineers with a cost-efficient method for heat and moisture transfer, and radon (Rn) gas elimination in a radioactive waste repository. The overall thermal performance of the repository may be improved. The dry-out period may be extended, and the seepage flux likely would be decreased.

• Computational Structural Engineering
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• v.18 no.1 s.67
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• pp.45-50
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• 2005

원자력 발전 과정에서 부산물로 발생되는 사용후 핵연료와 같은 고준위 방사성 폐기물은 수백 만년 동안 인간 및 자연 환경에 영향을 미치기 때문에 엄격한 관리가 요구된다. 이를 위하여 세계 각국에서는 스웨덴의 고준위방사성폐기물 처분개념인 KBS-3개념과 같이 고준위 방사성폐기물을 지하 500미터 심도의 암반에 영구 처분하기 위하여 많은 연구를 수행하고 있다. 이러한 연구 활동의 일환으로 고준위 방사성폐기물에서 발생하는 방사성 붕괴열로 인한 처분장 인접 암반에서의 응력 변화 및 이에 따른 주변 암반대에서의 지하수 유동 현상 규명을 위한 연구들 가운데 전산해석분야의 연구로 가장 활발히 진행되고 있는 것이 DECOVALEX 국제 공동 연구이다. 본고에서는 그 동안 진행되었던 DECOVALEX 연구 수행내용에 대하여 살펴보고자 한다.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.9 no.4
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• pp.103-112
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• 1989

A numerical model for Steady state groundwater flow has been established to understand the groundwater flow phenomena near a radioactive waste repository. The integrated finite difference method based on a network composed of nodes and members was applied to investigate groundwater flow in homogeneous, heterogeneous and layered media. Its numerical solution was in good agreement with analytic solution. Physical phenomena associated in the groundwater flow depending on both hydraulic characteristics and effects of fractured zone were also investigated. A method by which feasible groundwater flow paths can be identified was developed. This method used the composite network for the geologic media near a repository and the direction of computed groudwater velocity. Groundwater velocity and travel time were predicted for the possible pathway form a repository to a biosphere.

• The Journal of Engineering Geology
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• v.11 no.3
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• pp.255-267
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• 2001

A comparison study is performed to understand the coupling behavior of the thermal, hydraulic, and mechanical interactions in the vicinity of an underground radwaste repository, assumed to be located at a depth of 500 m, within a granitic rock mass with a 58$^{\circ}$ dipping fault passing through the roof-wall intersection of the repository cavern. The two dimensional universal distinct element code, UDEC is used for the analysis. The model includes a granitic rock meas, a canister with PWR spent fuels surrounded by the compacted bentonite inside a deposition hole, and the mixed bentonite backfilled in the rest of the space within a repository cavern. The coupling behavior of hydromechanical, thermomechanical, and thermohydromechanical interaction has been studied and compared. The effect of the time-dependent decaying heat, from the radioactive materials in PWR spent fuels, on the repository and its surroundings has been studied. A steady state flow algorithm is used for the hydraulic analysis.

• Magazine of korean Tunnelling and Underground Space Association
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• v.18 no.1
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• pp.29-49
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• 2016

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.229-234
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• 1996

방사성폐기물 영구처분장과 같은 대규모 지하 원자력시설의 운영중 안전성 평가를 위하여 지하 구조물의 지진 취약도 해석기법을 제안하였다. 지상구조물에 대해 적용되고 있는 Zion 방법을 모체로 하였으며 지하구조물의 특성 및 기술현황을 반영하였다. 지하구조물의 파괴양상은 구조물의 크기 및 형태, 수평 지압의 크기, 암반의 특성 등 많은 요인에 의해 달라진다. 처분동굴의 개념설계 결과에 대한 지진취약도 분석결과 수평지압계수의 영향이 매우 크며, 벽체부 또는 천정부에서의 숏크리트의 압축파괴가 가장 취약한 것으로 밝혀졌다.

• Nuclear Engineering and Technology
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• v.27 no.2
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• pp.260-268
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• 1995

국내 원자력발전소의 방사성폐기물 발생량은 초고압 압축, 농축폐액 건조, 페수지 건조 등의 폐기물감용을 위한 운영계획이 수립되고 또한 일부 원자력발전소에서는 1995년부터 운영이 시작될 예정이어서 감소가 예상되고 있다. 원자력발전소로부터 방사성폐기물의 누적량은 2035년까지 운영자의 폐기물 감용 계획을 고려한다면 141,920 드럼으로 예상할 수 있고, 이에 상응하는 방사능량은 반감기가 한달 이상인 30개 핵종에 대하여 방사성 붕괴를 무시할 때 49,390 Ci였다. 특히 원자력환경관리센터에서 수행한 개념설계에 따른 1차 건설예정의 지하 처분동굴의 적재량인 약 10만 드럼은 2014년까지 누적량으로 채울 수 있고 이때 처분장의 장기적 성능평가에 주요 고려 대상인 반감기가 5년 이상의 14개 핵종에 대한누적 방사능량은 약 13,577 Ci였다. 이 예측된 발생량과 재고량은 처분장 장기적 성능 및 안전성 평가에 중요한 기초자료가 될 것이다.

• Tunnel and Underground Space
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• v.12 no.1
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• pp.43-51
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• 2002

한국원자력연구소에서는 80년대 말부터 1996년까지 저준위 방사성 영구처분 연구사업을 수행한 바 있으며 2000년부터는 국가원자력중장기연구개발사업의 일환으로 한국원자력연구소와 한국수력원자력주식회사가 동굴 처분 관련 안전성 평가 연구를 공동 수행하고 있다. 본 기술 보고에서는 그 동안 개발된 연구 개발 성과들을 중심으로 중저준위 방사성폐기물 처분장 장기 안전성 평가에서 고려되어야 할 요소들과 현재까지 정립된 안전성 평가 방안들에 관하여 정리하였다.

• Tunnel and Underground Space
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• v.21 no.6
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• pp.518-525
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• 2011

In this study, the natural ventilation pressure resulting from the large altitude difference which is a characteristic of high radioactive waste repository and the caloric value of the heat emitted by wastes was calculated and based on the results, natural ventilation quantities were calculated. A high radioactive waste repository can be considered as being operated through closed cycle thermodynamic processes similar to those of thermal engines. The heat produced by the heating of high radioactive wastes in the underground repository is added to the surrounding air, and the air goes up through the upcast vertical shaft due to the added heat while working on its surroundings. Part of the heat added by the work done by the air can be temporarily changed into mechanical energy to promote the air flow. Therefore, if a sustained and powerful heat source exists in the repository, the heat source will naturally enable continued cyclic flows of air. Based on this assumption, the quantity of natural ventilation made during the disposal of high radioactive wastes in a deep geological layer was mathematically calculated and based on the results, natural ventilation pressure of $74{\sim}183$Pa made by the stack effect was identified along with the resultant natural ventilation quantity of $92.5{\sim}147.7m^3/s$. The result of an analysis by CFD was $82{\sim}143m^3/s$ which was very similar to the results obtained by the mathematical method.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.199-207
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• 2004

In order to develop a safe geological disposal concept for the HLW from the nuclear power plants in Korea, it is necessary to evaluate the safety of the disposal concept in an underground research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, geological investigation had been carried out to develop the basic design of the small scale underground disposal research tunnel in KAERI.