• Nuclear industry
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• v.5 no.11 s.33
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• pp.18-24
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• 1985

• Tunnel and Underground Space
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• v.33 no.5
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• pp.312-338
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• 2023

The underground disposal facility for spent nuclear fuel demands a specialized design, distinct from conventional practices, to ensure long-term thermal, mechanical, and hydraulic integrity, preventing the release of radioactive isotopes from high-temperature spent nuclear fuel. SKB has established design criteria for such facilities and executed practical design implementations for Forsmark. Moreover, in response to subsurface uncertainty, SKB has proposed an empirical approach involving monitoring and adaptive design modifications, alongside stepwise development. SKB has further introduced a unique support system, categorizing ground types and behaviors and aligning them with corresponding support types to confirm safety through comparative analyses against existing systems. POSIVA has pursued a comparable approach, developing a support system for Onkalo while accounting for distinct geological characteristics compared to Forsmark. This demonstrates the potential for domestic implementation of spent nuclear fuel disposal facility designs and the establishment of a support system adapted to national attributes.

• Tunnel and Underground Space
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• v.14 no.3
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• pp.175-187
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• 2004

고준위방사성폐기물 처분의 경우 심부 암반에 만들어진 처분장에 영구 처분하는 것이 최선의 방안으로 여겨지고 있다. 하지만 지하 심부의 암반에 대한 물리적, 화학적, 역학적, 열적, 수리적 물성과 이들과 핵종 이동의 관계, 처분환경에서의 공학적 방벽 및 암반의 거동이 처분장 안정성 및 안전성에 미치는 영향 등을 파악해야하는 어려움이 따른다. 특히 고준위폐기물 처분의 경우 장기간의 안전성을 고려해야하기 때문에 자연방벽과 공학적 방벽의 시간에 따른 거동변화도 고려하여야 할 필요가 있다. (중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.2
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• pp.179-188
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• 2016

Spent fuels from nuclear power plants, as well as high-level radioactive waste from the recycling of spent fuels, should be safely isolated from human environment for an extremely long time. Recently, meaningful studies on the development of deep borehole radioactive waste disposal system in 3-5 km depth have been carried out in USA and some countries in Europe, due to great advance in deep borehole drilling technology. In this paper, domestic deep geoenvironmental characteristics are preliminarily investigated to analyze the applicability of deep borehole disposal technology in Korea. To do this, state-of-the art technologies in USA and some countries in Europe are reviewed, and geological and geothermal data from the deep boreholes for geothermal usage are analyzed. Based on the results on the crystalline rock depth, the geothermal gradient and the spent fuel types generated in Korea, a preliminary deep borehole concept including disposal canister and sealing system, is suggested.

• Tunnel and Underground Space
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• v.32 no.6
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• pp.435-450
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• 2022

In step-by-step site selection for geological disposal of high-level radioactive waste, parameters necessary for site selection will be acquired through deep drilling surveys from the basic survey stage. Unlike site investigations of rock mass structures such as tunnels and underground oil storage facilities, those related to the geological disposal of high-level radioactive waste are not only conducted in relatively deep depths, but also require a high level of quality control. In this report, based on the 750 m depth drilling experience conducted to acquire the parameters necessary for deep geological disposal, the methodology for deep drilling and the geology, geophysics, geochemistry, hydrogeology and rock mechanics obtained before, during, and after deep drilling are discussed. The procedures for multidisciplinary geoscientific investigations were briefly described. Regarding in-situ stress, one of the key evaluation parameter in the field of rock engineering, foreign and domestic cases related to the geological disposal of high-level radioactive waste were presented, and variations with depth were presented, and matters to be considered or agonized in acquiring evaluation parameters were mentioned.

• Nuclear industry
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• v.23 no.1 s.239
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• pp.64-78
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• 2003

한국원자력연구소에서는 과학기술부에서 주관하는 국제 협력 기반 조성 사업 과제의 일환으로 한국-핀란드 양국간 원자력 협력 증진을 위한 프로젝트를 수행하고 있다. 특히 이 연구에서는 방사성 폐기물 관리와 관련된 양국간 이해 증진과 향후 협력을 모색하기 위한 방안을 수립하고자 하였다. 본 연구에서는 이와 같은 관점에서 세계 최초로 사용후 핵연료 영구 처분장 부지를 확보하고 우리나라와 지질 조건이 유사한 결정질 암반에 신규로 심지층 처분 연구 실증 시설인 온칼로(Onkalo) 프로젝트를 계획하고 있는 핀란드의 방사성 폐기물 관리기관인 POSIVA 등과 관련 협력 기관, 정부 기관 등과 함께 향후 구체적인 협력 방안을 모색하고, 핀란드의 사용후 핵연료 직접 처분 연구사업 계획을 벤치 마킹하여 2003년도에 시작하는 국내 고준위 방사성 폐기물 처분 연구 과제 계획 수립에 도움을 주고자 하였으며, 이와 병행하여 핀란드 신규 원전 사업과 관련된 국내 산업체의 참여 가능성을 타진해 보고자 하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.3
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• pp.183-190
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• 2009

The basic function of HLW disposal system is to prevent excessive radio-nuclides being leaked from the repository in a short time. To do this, many technical standards should be developed and established on the components of disposal system. Safety assessment of a repository is considered as one of technical standards, because it produces quantitative results of the future evolution of a repository based on a reasonably simplified model. In this paper, we investigated other countries' regulations related to safely assessment focused on the assessment period, radiation dose limits and uncertainties of the assessment. Especially, in the investigation process of the USA regulations, the USA regulatory bodies' approach to assessment period and peak dose is worth taking into account in case of a conflict between peak dose from safety assessment and limited value in regulation.

• Nuclear Engineering and Technology
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• v.24 no.3
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• pp.329-335
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• 1992

장반감기 초우라늄 원소들(Am, Cm, Np 등)과 핵분열생성물들(135Cs, 129I)이 포함된 고준위 방사성폐기물을 심지층처분할 경우도 장반감기 핵종들의 장시간에 걸친 유출현상으로 인하여 환경오염이 문제가 될 가능성이 있다. 이러한 장반감기 핵종들의 심지층처분 대안으로 소멸처리 방식이 70년대부터 선진국들에서 활발히 연구되어져 왔다. 본 기고문은 이러한 소멸처리와 그 전단계인 군분리 기술의 현황과 향후 전망을 정리하고 특히 현존하는 소멸처리 방식의 문제점을 분석하여 향후 국내에서 수행할 소멸처리 연구에 도움이 되고자 하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.168-171
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• 2003

The IMEF(Irradiated Materials Examination Facility), located in KAERI site, is a hot cell facility to test and evaluate the irradiation defects or embrittlement through post-irradiation examination(PIEs) of irradiated nuclear fuels and structural materials which are come from HANARO research reactor and commercial nuclear power plants. Therefore, to carry out its own function, the high level solid radioactive wastes, produced through PIEs, are periodically carried out and managed from hot cell to monolith. So far, approximately 30 drums which contains 50 liters are transported to monolith, and it is shown that the quantity is slowly increasing, In this paper, the procedures and work contents of the high level solid radwaste carrying out and management for IMEF are described in detail.

• Geotechnical Engineering
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• v.40 no.5
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• pp.8-29
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• 2024