• 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.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.4
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• pp.369-380
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• 2017

In order to manage the uncertainty about the evaluation and analysis of the human intrusion scenario of the Gyeongju Low and Intermediate Level Radioactive Waste(LILW) disposal facility, the calculation result by the GENII code was assessed using the RESRAD code, which was developed to evaluate the radiation effects of contaminated soil. The post-drilling scenario was selected as a human intrusion scenario into the near-surface disposal facility to analyze the uncertainty of the modeling by identifying any limitations in the simulation of each code and comparing the evaluation results under the same input data conditions. The results revealed a difference in the migration of some nuclides between the codes, but confirmed that the dose trends at the end of the post-closure control period were similar for all exposure pathways. Based on the results of the dose evaluation predicted by RESRAD, sensitivity analysis on the input factors was performed and major input factors were derived. The uncertainty of the modeling results and the input factors were analyzed and the reliability of the safety evaluation results was confirmed. The results of this study can be applied to the implementation 'Safety Case Program' for the Gyeongju LILW disposal facility.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.1
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• pp.45-54
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• 2008

A new proposed repository has a final capacity of 800,000 drums radioactive waste. Most of foreign repositories have a general practice of segregating control zones which mainly contributes to classification of degree of control, whether it is called buffer zone or not. Domestic regulatory requirements of establishment of buffer zone in a repository are not much different from those of nuclear power plants for operation period, in which satisfactory design objective or performance objective is the most important factor in determination of the buffer zone. The meaning of buffer zone after closure is a minimum requested area which can prevent inadvertant intruders from leading to non-allowable exposure during institutional control period. Safety assessment with drinking well scenario giving rise to the highest probability of exposure among the intruder's actions can verify fulfillment of the buffer zone which is determined by operational safety of the repository. At present. for the repository to be constructed in a few years, the same procedure and concept as described in this paper are applied that can satisfy regulatory requirements and radiological safety as well. However, the capacity of the repository will be stepwise extended upto 800,000 drums, consequently its layout will be varied too. Timely considerations will be necessary for current boundary of the buffer zone which has been established on the basis of 100,000 drums disposal.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.219-228
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• 2012

A long-term R&D program for HLW disposal technology development was launched in 1997 in Korea and Korea Reference disposal System(KRS) for spent fuels had been developed. After then, a recycling process for PWR spent fuels to get the reusable material such as uranium or TRU and to reduce the volume of radioactive waste, called Pyro-process, is being developed. This Pyro-process produces several kinds of wastes including metal waste and ceramic waste. In this study, the characteristics of the waste from Pyro-process and the concepts of a disposal container for the wastes were described. Based on these concepts, thermal analyses were carried out to determine a layout of the disposal area of the ceramic wastes which was classified as a high level waste and to develop the disposal system called A-KRS. The location of the final repository for A-KRS is not determined yet, thus to review the potential repository domains, the possible layout in the geological characteristics of KURT facility site was proposed. These results will be used in developing a repository system design and in performing the safety assessment.

• Economic and Environmental Geology
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• v.56 no.6
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• pp.887-897
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• 2023

Leading waste disposal countries, such as Sweden, Switzerland, and the United Kingdom, conduct safety assessments across all stages of High-Level Radioactive Waste Deep Geological Disposal Facilities-from planning and site selection to construction, operation, closure, and post-closure management. As safety assessments are repeatedly performed at each stage, generating vast amounts of diverse data over extended periods, it is essential to construct a database for safety assessment and establish a data management system. In this study, the safety assessment data management systems of leading countries, were analyzed, categorizing them into 1) input and reference data for safety assessments, 2) guidelines for data management, 3) organizational structures for data management, and 4) computer systems for data management. While each country exhibited differences in specific aspects, commonalities included the classification of safety assessment input data based on disposal system components, the establishment of organizations to supply, use, and manage this data, and the implementation of quality management systems guided by instructions and manuals. These cases highlight the importance of data management systems and document management systems for securing the safety and enhancing the reliability of High-Level Radioactive Waste Disposal Facilities. To achieve this, the classification of input data that can be flexibly and effectively utilized, ensuring the consistency and traceability of input data, and establishing a quality management system for input data and document management are necessary.

• Nuclear industry
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• v.26 no.8 s.282
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• pp.15-28
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• 2006

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.4
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• pp.191-205
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• 2009

To characterize the geological features in the study area for high-level radioactive waste disposal research, KAERI (Korea Atomic Energy Research Institute) has been performing several geological investigations such as geophysical surveys and borehole drillings since 1997. Especially, the KURT (KAERI Underground Research Tunnel) constructed to understand the deep geological environments in 2006. Recently, the deep boreholes, which have 500 m depth inside the left research module of the KURT and 1,000 m depth outside the KURT, were drilled to confirm and validate the results from a geological model. The objective of this research was to investigate hydrogeological conditions using a 3-D geological model around the KURT. The geological analysis from the surface and borehole investigations determined four important geologicla elements including subsurface weathered zone, low-angled fractures zone, fracture zones and bedrock for the geological model. In addition, the geometries of these elements were also calculated for the three-dimensional model. The results from 3-D geological model in this study will be beneficial to understand hydrogeological environment in the study area as an important part of high-level radioactive waste disposal technology.

• Proceedings of the Korean Society for Rock Mechanics Conference
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• 2004.04a
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• pp.123-140
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• 2004

저준위 방사성폐기물 안전성 평가를 위해서 안전성 평가 대상에 관한 기술이 이해당사자들이 이해하기 명확하고 쉽게 설정되어야 한다. 방사선적 안전성 평가 시나리오란 처분장으로부터 유출된 방사성 물질들이 공학적 방벽과 천연 방벽을 거쳐 생태계로 어떻게 이동하는가에 대한 설명으로 안전성 평가를 위한 일종의 대본과 같은 역할을 한다. 본 논문에서는 핵종 이동 현상을 RES(Rock Engineering System) 방법론에 의거 기술하였다. 국내 처분장의 특성을 고려하여 처분 시설은 연안에 동굴 처분 방식으로 건설된다고 가정하여 생태계를 산정하고, 공학적 및 천연 방벽들이 처분장 설계 시 예상한 기능들을 수행한다고 가정하여, 기준 시나리오를 설정하였다. 또한 다양한 설계 고려 요소들을 고려하여 대안 시나리오들을 도출하고자 하였다. 도출된 시나리오의 주요 항목들을 평가하기 위해서 AMF(Assessment Method Flowchart)를 도출하였다. 주어진 지형 조건에 따라 확률론적 방사선적 안전성 평가를 위해 각 지층 구조별 이동 거리 및 시간을 CONNECTFLOW를 이용해 산정하고, 그 결과들을 Response surface method를 이용해 확률 밀도함수로 도출하여 방사선적 안전성 종합 평가 코드인 MASCOT-K의 입력 자료로 활용되도록 하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.11a
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• pp.233-234
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• 2006

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.221-230
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• 2005

To support the design concept and performance evaluation of the cover system for low- and intermediate-level radioactive waste(LILW) disposal facility, the pioneering study is conducted with the tomb of historical age. Research status of the art are followed and the characteristics of tomb cover are summarized based on the preservation of historical remains. Visiting the excavation site of historical tomb and communication with Korean archeological society is required for the further understanding and for the extension of radioactive waste disposal research.