• Nuclear industry
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• v.6 no.12 s.46
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• pp.120-122
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• 1986

미국원자력학회가 주최한 ${\ulcorner}$SPECTRUM '86-폐기물처리처분 및 제염과 폐로회의${\lrcorner}$가 '세계의 방사성폐기물관리 현황과 장래'를 기조테마로 지난 9월 14일부터 18일까지 17개국에서 600여명이 참가한 가운데 열려, 고$\cdot$저준위폐기물처리처분에 대한 경험과 계획, 제염과 폐로 등에 관해서 폭넓게 논의되었다. 다음은 이 회의에서 소개된 선진각국에서의 유리고화플랜트 현황과 처분계획을 요약한 것이다.

• Proceedings of the Korean Society for Rock Mechanics Conference
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• 2006.03a
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• pp.205-213
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• 2006

본고에서는 해외사례의 조사/분석을 통해 국내 환경에 적합한 처분시스템을 개발하는데 효율적으로 이용할 목적으로 일본의 방사성 폐기물 처분과 관련한 주요기관의 사업내용을 정리하고 암석역학 전공자가 관심을 가져볼 만한 처분 관련 연구시설 및 연구내용을 소개한다. 저준위 폐기물을 대상으로 한 100m 심도의 롯까쇼무라 시험공동과 고준위 폐기물을 대상으로 결정암질에 건설되는 1000m 심도의 미즈나미 지하연구시설 및 퇴적암질에서의 500m 심도의 호로노베 지하연구시설을 소개하였다.

• 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.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2001.11a
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• pp.331-336
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• 2001

한국원자력연구소에서는 고준위 방사성폐기물 처분 시스템의 안전성을 투명하게평가하기 위한 방안의 하나로 처분 안전성 관련 시나리오와 구성 요소들인 FEP, 그리고 각 시나리오 별 안전성 평가 방안들을 종합한 프로그램인 FEAS를 개발하고 있다. 고준위 방사성 폐기물 처분 연구는 관련 전문가 뿐 아니라 일반 국민들도 안전성에 관해 많은 관심을 표명하고 있는 바 현재 국내에서 고려하고 있는 처분 개념은 무엇이며 처분장 안전성 평가를 위해서 고려하고 있는 제 사건들은 무엇이며 이들 시나리오를 구성하는 세부 사건들은 무엇인가에 관한 합의를 도출하고 이와 관련된 기록들을 보존하고 각각 세부 사건들에 관해 현재의 평가 방안과 데이터 수집 현황 그리고 해외 사례 등을 체계적으로 정리하는 일은 중요하다. 현재 개발되고 있는 FEAS는 이와 같은 역할을 수행할 뿐 아니라 이 프로그램과 동시에 개발되고 있는 입력 자료 데이터 시스템, 웹을 기반으로 한 품질 보증 체제 및 안전성 평가 방안 등과 향후 연계되어 모든 국민들이 방사성 폐기물 처분장의 안전성을 쉽게 이해할 수 있는 수단으로 확장될 예정이다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.1
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• pp.65-82
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• 2017

The result of a preliminary safety assessment that was completed by applying the radionuclide inventory calculated on the basis of available data from radioactive waste generation agencies suggested that many difficulties are to be expected with regard to disposal safety and operation. Based on the results of the preliminary safety assessment of the entire disposal system, in this paper, a unit package exceeding the safety goal is selected that occupies a large proportion of radionuclides in intermediate-level radioactive waste. We introduce restrictions on the amount of radioactivity in a way that excludes the high surface dose rate of the package. The radioactivity limit for disposal will be used as the baseline data for establishing the acceptance criteria and the disposal criteria for each disposal facility to meet the safety standards. It is necessary to draw up a comprehensive safety development plan for the Gyeongju waste disposal facility that will contribute to the construction of a Safety Case for the safety optimization of radioactive waste disposal facilities.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.199-207
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• 2004

In order to develop a safe geological disposal concept for the HLW from the nuclear power plants in Korea, it is necessary to evaluate the safety of the disposal concept in an underground research tunnel in the same geological formation as the host rock mass. The design concept of a research tunnel depends on the actual disposal concept, repository geometry, experiments to be carried at the tunnel, and geological conditions. In this study, geological investigation had been carried out to develop the basic design of the small scale underground disposal research tunnel in KAERI.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.4
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• pp.305-320
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• 2016

The metal waste generated during nuclear power plant decommissioning constitutes a large proportion of the total radioactive waste. This study investigates the current status of domestic and international regulatory requirements for clearance and the clearance experience of domestic institutions. The RESRAD-RECYCLE code was used for analyzing the clearance of the metal wastes generated during actual nuclear power plant decommissioning, and assessment of the exposure dose of twenty-six scenarios was carried out. The evaluation results will be useful in preliminary analysis of clearance and recycling during nuclear power plant decommissioning. As a next step, the effects of reducing disposal costs by clearance can be studied.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.10a
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• pp.157-158
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.205-206
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• 2016

• Tunnel and Underground Space
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• v.26 no.5
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• pp.339-347
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• 2016

The world's first underground repository for low- and intermediate- level radioactive waste (SFR1) has been in operation since 1988. SFR1 can accommodate $1,000m^3$ of radioactive waste per year with 4 chambers and 1 silo with a total capacity of $63,000m^3$ of radioactive waste. With extended operation time of 10 of the 12 nuclear power reactors and dismantling of the other 2 nuclear reactors, more nuclear waste need to be disposed in the future. Therefore, Swedish Nuclear Fuel and Waste Management Company (SKB) submitted a license application for a repository extension (SFR3) that consists of 6 additional rock chambers with a capacity of $108,000m^3$ of radioactive waste and for accommodating 9 boiling water reactor tanks. In this study, plans for the extension SFR3 are presented with the geological, geomechanical and hydrogeological issues to be considered.