• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.357-368
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• 2008

On July 31, 2008, the Government issued the construction and operation permit for the first low and intermediate level radioactive waste disposal facility in the Republic of Korea. In this paper, the fundamental regulatory framework, regulatory requirements and technical standards of the disposal facility are introduced, and the phased review process adopted for evaluation of the safety of the facility is briefly described. The Atomic Energy Act sets forth a stepwise regulatory framework for the whole life-cycle of the disposal facility such as siting, design, construction, operation, closure and institutional control. More detailed regulatory requirements and technical standards are stipulated in the subsequent regulations of the Atomic Energy Act and a series of Notices issued by the Ministry of Eduction, Science and Technology. The Korea Institute of Nuclear Safety, as entrusted by the Ministry under the Atomic Energy Act, conducted safety review on the disposal facility, and evaluated the compliance with relevant criteria in all technical elements(i.e. siting and structural safety, radiological environmental impact, operational safety, systems and components, quality assurance, and total systematic performance assessment, etc.). The overall safety review process can be phased into inception phase, initial review phase, main review phase and completion phase. The review results were reported to and deliberated by the five Sub-committees of the Special Committee on Nuclear Safety, and then reported to the Ministry. The Ministry issued the construction and operation permit of the disposal facility through the deliberation of the review results by the Nuclear Safety Commission. Hereafter, the safety of the repository will be reassured by a series of subsequent regulatory inspections and reviews under the Atomic Energy Act. In addition, the licensee's continuous implementation of the "Safety Promotion Plan" may also enhance the long-term safety of the repository and contribute to build-up the confidence of the safety case.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.447-452
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• 1998

우리나라에서도 고준위폐기물 처분시설의 장기안전성 확보를 위한 기초연구가 시작되고 있어 안전성 기준에 대한 논의가 필요한 시점이다. 여기서는 고준위폐기물 처분시설의 안전성 기준에 대한 국제기관들의 권고하는 기준들을 조사하고, 현재 여러 나라에서 제안되거나 개정중에 있는 기준들을 비교 분석하였다. 안전성기준에서의 큰 차이점은 유도기준의 필요성(현재 미국만의 유도기준을 사용), ALARA 적용문제, 종합적 위험도 적용방법론의 문제, 위험도 수준등에서 나타나고 있으며, 특히 미래 상황의 불확실성 때문에 현재 및 개 국가에서 제시하고 있는 안전성평가기간 (10,000면)은 계속 논란이 일 것으로 보인다. 미래 예측이 어느 정도 가능한 최소한의 기간(수천년 혹은 만년)까지는 위험도를 기준으로, 그리고 그 이후는 지표로의 누출율을 기준으로 정하는 것도 바람직한 대안이 될 것으로 생각된다. 또한 안전성기준은 설계자로 하여금 대안분석을 통한 최적화를 방해하는 구체적인 유포기준보다는 융통성을 어느 정도 부여하는 방향으로 설정되는 것이 바람직한 것으로 사료된다.

• 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.

• 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.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.283-289
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• 2003

In order to establish the licensing review system for LILW disposal facility, we have studied the licensing review structure of oversea's countries, including United State, Japan, and France. We have also reviewed the domestic licensing review structure and the current status of development of safety standards for LILW management. A licensing review for LILW disposal facility can be implemented in 5-6 steps according to Atomic Energy Act. It is estimated to take 32 months for the CP and the OL review for LILW disposal facility referencing to the licensing review practice of the nuclear power plant. To date, a total of 15 MOST Notices have been developed to apply to the safe management of radwaste and 5 more MOST Notices will be developed by 2005.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.219-230
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• 2017

This study was conducted to predict and evaluate the uncertainty of safety after closure of the second phase surface disposal facility of the Gyeongju intermediate and low level repository in Korea. In this study, four scenarios are developed considering both intact and degraded states of multi-layered covers and disposal containers; also, the fluid flow by a rainfall into the disposal facility is simulated. The rainfall conditions are implemented based on the monthly average data of the past 30 years (1985~2014); the simulation period is 300 years, the management period regulated by institutional provisions. As a result of the evaluation of the basic scenario, in which the integrity of both of the containers and the covers is maintained, it was confirmed that penetration of rainfall does not completely saturate the inside of the disposal facility. It is revealed that the multiple cover layers and concrete containers effectively play the role of barrier against the permeation of rainfall.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.251-252
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.207-208
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.379-380
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.231-232
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• 2009