Since the first operation of the Gori No. 1 nuclear power plant in Korea was started to operate in 1978, currently 24 nuclear power plants have been being operated, out of which 21 plants are PWR types and the rest are CANDU types. About 30% of total electricity consumed in Korea is from all these nuclear power plants. The accumulated spent nuclear fuels (SFs) generated from each site are temporarily being stored as wet or dry storage type at each plant site. These SFs with their high radiotoxicity, heat generating, and long-lived radioactivity are actually the only type of high-level radioactive waste (HLW) in Korea, which urgently requires to be disposed of in deep geological repository. Studies on disposal of HLW in various kind of geological repositories have been carried out in such countries as Sweden, Finland, United States, and etc. with their own methodologies and management policies in consideration of their situations. In Korea long-term R&D research program for safe management of SF has also been conducted during last couple of decades since around 1997, during which several various alternative type of disposal concepts for disposal of SNFs in deep geological formations have been investigated and developed. The first concept developed was KAERI Reference Disposal System (KRS) which is actually very much similar to Swedish KBS-3, a famous concept of direct disposal of SF in stable crystalline rock at a depth of around 500 m which has been regarded as one of the most plausible method worldwide. The world first Finnish repository which is expected to begin to operate sooner or later will be also this type. Since the characteristics of SF discharged from domestic nuclear reactors have been changed and improved, and burnup has sometimes increased, a more advanced deep geological repository system has been needed, KRS-HB (KRS with High Burnup SF) has been developed and in consideration of the dimensions of SNFs and the cooling period at the time point of the disposal time, KRS+, a rather improved disposal concept has also been subsequently developed which is especially focused on the efficient disposal area. Recently research has concentrated on rather advanced disposal technology focused on a safer and more economical repository system in recent view of the rapidly growing amount of accumulated SF. Especially in Korea the rock mass and the footprint area for the repository extremely limited for disposal site. Some preliminary studies to achieve rather higher efficiency repository concept for disposal of SF recently have already been emphasized. Among many possible ones for consideration of design for high-efficiency repository system, a double-layered system has been focused which is expected to maximize disposal capacity within the minimum footprint disposal area. Based on such disposal strategy a rather newly designed performance assessment methodology might be required to show long-term safety of the repository. Through the study some prerequisites for such methodological development has been being roughly checked and investigated, which covers FEP identification and pathway and scenario analyses as well as preliminary conceptual modeling for the nuclide release and transport in nearfield, far-field, and even biosphere in and around the conceptual repository system. Through the study such scenarios and models has been implemented to development of a safety assessment by utilizing GoldSim development tool for a rough quantitative comparison with existing disposal options and simple illustration purpose as well as for showing how to develop and implementation of the model to GoldSim templet.

고준위 방사성폐기물로 분류되는 사용후핵연료를 현재 기술로 가장 안전한 격리 방법으로는 500 m 심도의 안정한 암반에 심지층 처분하는 방법으로, 가장 중요한 요건은 공학적방벽인 완충재의 온도가 100℃를 초과하지 않도록 시스템을 설계하 는 것이다. 국내의 경우 전체 전력 소요량의 약 30% 정도를 차지하고 있는 원자력발전으로 발생되는 사용후핵연료의 양은 지속적으로 증가하여 누적되고 있어, 이들을 처분하기 위한 소요면적도 증가하고 있다. 따라서, 본 연구에서는 처분면적을 감소시킴으로써 처분효율을 향상시키기 위한 목적으로 다양한 복층처분 개념을 도출하였다. 이를 바탕으로 중요한 처분시 스템 요건 만족여부를 확인하기 위하여 열해석을 수행하고 그 결과를 분석하여 처분시스템 열적 안정성을 평가하였다. 평 가결과, 기준시스템 위치인 500 m 심도로부터 상부 또는 하부로 75 m를 이격한 심도에 복층으로 처분시스템 구축이 가능 하였으며, 실제 부지특성자료에 따른 상세 분석이 요구된다. 본 연구결과는 사용후핵연료 관리정책 수립 및 실제 처분시스 템 설계에 활용될 것으로 사료된다.