• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2014.10a
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• pp.363-364
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• 2014

국내 에너지의 장기적인 수요상황을 볼 때 원자력 발전의 비중이 확대되는 것은 불가피 하므로 환경 친화적인 사용 후 핵연료의 관리 및 고준위 폐기물의 처분방안의 마련은 원자력의 개발만큼이나 중요하다. 이에 본 연구에서는 방사성 폐기물의 효율적인 관리와 저장 및 열제거를 위하여 최적 환기시스템을 적용한 처분장 설계를 목적으로 여러 환기시스템 설계안을 비교 분석하였다. 분석결과, 8가지 중 case 4(병렬회로)와 case 6(혼합 Diagonal 회로)의 환기효율이 우수한 결과를 나타냈으며, 이와 같은 연구를 통해 환경 친화적인 처분장의 건설이 가능할 것이다.

• Nuclear industry
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• v.22 no.8 s.234
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• pp.8-14
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• 2002

• Tunnel and Underground Space
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• v.7 no.3
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• pp.246-252
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• 1997

원자력 발전 과정에서 부산물로 발생되는 사용후 핵연료와 같은 고준위 방사성폐기물은 수백 만년동안 인간 및 자연 환경에 영향ㅇ르 미치기 때문에 엄격한 관리가 요구된다. 이를 위하여 세계 각국에서는 KBS-3 개념과 같이 고준위 방사성폐기물을 지하 500미터 심도의 암반에 영구 처분하기 위하여 연구를 수행사고 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 연구가 지난 1980년대부터 활발하게 진행되고 있는 바, 그 대표적인 연구 과제가 DECOVALEX 국제 공동 연구이다. 이 글에서는 현재 진행 중인 DECOVALEX 연구 현황과 향후 전망에 관하여 조명하고자 한다.

• Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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• 2001.04a
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• pp.81-84
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• 2001

고준위 방사성 폐기물 영구처분 안전성을 평가하기 위하여 입력 자료로 처분장 주변 각 암 반에서의 지하수 유동 속도 및 유동 시간이 요구된다. 이러한 유동 속도와 시간은 대부분의 경우 단일 값이 요구되지만 고준위 방사성 처분의 경우 지하 매질의 불확실성을 고려하기 위하여 확률론적 분석이 요구된다. 지하수 유동 속도 및 시간이 확률밀도함수로 표시되기 위해서는 기존의 방법에서는 수리 해석의 입력 인자 값들을 변화시키면서 반복적인 계산을 수행하는 방법이 사용되었다. 그러나 이러한 방법론의 한계를 극복하기 위해 최근 섭동 이론을 이용한 adjoint 방법론이 사용되고 있는 바 이를 이용하여 가상 처분장에서의 지하수 유동 속도와 시간을 확률론적으로 해석하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.133-141
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• 2012

The impacts influenced on the performance and safety of a repository are classified as units of Features, Events, and Processes (FEP), for the total system performance assessment (TSPA) related to the permanent disposal of HLW. The importance is evaluated in consideration of the frequency, consequence, regulation, suitability of a specific site, etc. and then these are grouped as a similar FEP. A scenario describing the migration of radionuclide from the repository to the biosphere is derived from understanding the interaction among these groups. KAERI has developed the KAERI FEP lists by review and collation of the foreign studies. The KAERI FEP list has been reviewed by several Korean experts. The five major scenarios describing possible future evolutions of the geological disposal system have been developed by RES and PID methods. Also the CYPRUS which is a KAERI integrated database management system for the total system performance assessment (TSPA) related to the permanent disposal of HLW has been developed and the results of the FEP and scenario development have been uploaded in this system.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.281-294
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• 2012

The current status of the computer codes for the analysis of coupled thermal-hydrological-mechanical behavior occurred in a high-level waste repository was investigated. Based on the reported results on the comparison between the predictions using the computer codes and the experimental data from the in-situ tests, the reliability of the existing computer codes was analyzed. The presented codes simulated considerably well the coupled thermal-hydrological-mechanical behavior in the near-field rock of the repository without buffer, but the predictions for the engineered barrier system of the repository located at saturated hard rock were not satisfactory. To apply the current thermal-hydrological-mechanical models to the assessment of the performance of engineered barrier system, a major improvement on the mathematical models which analyze the distribution of water content and total pressure in the buffer is required.

• Tunnel and Underground Space
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• v.22 no.3
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• pp.173-180
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• 2012

In this study, diagonal ventilation circuits that are advantageous in air flow direction control were studied. Based on the results of the study, it could be seen that air volumes in diagonal ventilation circuits could also be calculated using numerical formulas or programs if the air volumes and air flow directions to be infused into diagonal branches are determined in advance as with other serial/parallel circuits. To apply the results, design plans for high level radioactive waste repositories applied with diagonal ventilation circuits and parallel ventilation circuits. To compared the each design plans and obtain expected operation results, ventilation network simulations were conducted through the Ventsim program which is a ventilation networking program. Based on the results, in the case of diagonal repositories that was expected to cause great increases in resistance, fan pressure was 1570 pa, total flux was 84 $m^3/s$, fan efficiency was 76.4%, fan power consumption was 181.2 kW and annual fan operating costs were 178,710,838 and thus maximum around 8% differences were shown in pressure and flux values and a difference of around 1.5% was shown in terms of operating costs.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.2
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• pp.105-112
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• 2004

A waste container, one of the key components of a multi-barrier system in a potential high level radioactive waste (HLW) repository in Korea ensures the mechanical stability against the lithostatic pressure of a deep geologic medium and the swelling pressure of the bentonite buffer. Also, it delays potential release of radionuclides for a certain period of time, before it is corroded by intruding impurities. Even though the material of a waste container is carefully chosen and its manufacturing processes are under quality assurance processes, there is a possibility of initial defects in a waste container during manufacturing. Also, during the deposition of a waste container in a repository, there is a chance of an incident affecting the integrity of a waste container. In this study, the appropriate Features, Events, and Processes(FEP's) to describe these incidents and the associated scenario on radionuclide release from a container to the biosphere are developed. Then the total system performance assessment on the Initial waste Container Failure (ICF) scenario was carried out by the MASCOT-K, one of the probabilistic safety assessment tools KAERI has developed. Results show that for the data set used in this paper, the annual individual dose for the ICF scenario meets the Korean regulation on the post closure radiological safety of a repository.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.20 no.2
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• pp.157-164
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• 2007

The prediction of the temperature distribution change of the spent nuclear fuel disposal canister and its surrounding structures (bentonite buffer, granitic rock etc.) due to the spent fuel heat is very important for the design of the 500m deep granitic repository for the spent nuclear fuel disposal canister (about 10,000 years long) deposition. In this study, the temperature distribution change of the composite structure which comprises the canister, the bentonite buffer, the deposition tunnel due to the spent fuel heat is computed using the numerical analysis method. Specially, the temperature distribution change of the composite structure is analysed as the deposition time elapses up to m years. The analysis result shows that the temperature of each part of the repository increases slowly in different way but the latest part temperature increases slowly up to 150 years and thereafter decreases slowly.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.1
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• pp.55-62
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• 2012

As an alternative of the high-level radioactive waste disposal in the subsurface repository, a deep borehole disposal is reviewed by several nuclear advanced countries. In this study, the state of the art on the borehole disposal researches was reviewed, and the possibility of borehole disposal in Korean peninsula was discussed. In the deep borehole disposal concept radioactive waste is disposed at the section of 3 - 5km depth in a deep borehole, and it has known that it has advantages in performance and cost due to the layered structure of deep groundwater and small surface disposal facility. The results show that it is necessary to acquisite data on deep geologic conditions of Korean peninsula, and to research the engineering barrier system, numerical modeling tools and disposal techniques for deep borehole disposal.