• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.171-172
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• 2010

본 논문에서는 하나로폐기물을 처분 원가대상으로 설정하고 처분 단위모듈당 주요 원가를 추정하였다. 추정결과, 처분용기 직접재료비가 제일 많이 소요되며, 그 다음은 처분공 굴착비인 것으로 나타났다. 이러한 이유는 처분공 굴착은 발파공법이 아닌 그라인더로 굴착하는 정밀공법이기 때문에 굴착단가가 1,143,963원/$m^3$으로 매우 비싸기 때문이다. 따라서 주요 원가동인의 비용 점유율은 처분용기 재료비가 44.7%, 처분공 굴착비가 27%로 나타났다. 그리고 처분터널 굴착비는 비교적 비용 점유율이 적은 2.3%로 계산되었다. 이러한 이유는 처분터널은 처분공과 달리 발파기법으로 굴착하기 때문에 굴착단가가 처분공 굴착단가에 비해 저렴하기 때문이다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.813-818
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• 1995

방사성 폐기물 처분장의 확률론적 안전성 분석은 방사성 폐기물 처분장의 운영에 앞서 수행되어야 할 과제이다. 따라서, 본 연구에서는 폐기물 처분장의 확률론적 안전성 분석을 체계적으로 수행하기 위한 방법론을 개발하여 제시하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.261-265
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• 2003

This paper proposes acceptance requirements and the corresponding implementation strategy for the near-surface repository of low- and intermediate-level radioactive wastes. The proposed requirements include details on waste classification and radionuclide concentration limitation and inventory analysis. The strategy considers a relevant linking between predisposal waste management, disposal safety assessment and the overall disposal system.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.143-152
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• 2005

There certainly exists the radioactive inventory that exceeds the waste acceptance criteria for final disposal of the low and intermediate-level radioactive waste. In this paper, current disposal status of the long-lived radioactive waste in several nations are summarized and the basic procedures for disposal approach are suggested. With this suggestion, intensive discussion and research activities can hopefully be launched to set down the possible resolutions to dispose of the long-lived radioactive waste.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.9 no.2
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• pp.87-92
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• 2011

This paper introduces the policy and regulations on very low level waste (VLLW) management in China. Given the important decommissioning and site restoration program of the old facility, it is considered necessary to create a new disposal facility dedicated to VLLW. Many general design principles are in common with to the disposal facility for low and intermediate level waste (LILW), namely the isolation of the waste by means of a multibarrier system, but using bentonite and/or high density polyethylene membranes instead of the generalized use of concrete barriers. The design of the facility is consistent with the design of disposal facilities for hazardous waste. The engineering design of two VLLW disposal facilities is introduced.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.3
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• pp.229-238
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• 2007

In this paper, structural design requirements and safety evaluation criteria of the spent nuclear fuel disposal canister are studied for deep geological deposition. Since the spent nuclear fuel disposal canister emits high temperature heats and much radiation, its careful treatment is required. For that, a long term(usually 10,000 years) safe repository for the spent nuclear fuel disposal canister should be secured. Usually this repository is expected to locate at a depth of 500m underground. The canister which is designed for the spent nuclear fuel disposal in a deep repository in the crystalline bedrock is a solid structure with cast iron insert, corrosion resistant overpack and lid and bottom, and entails an evenly distributed load of hydrostatic pressure from underground water and high pressure from swelling of bentonite buffer. Hence, the canister must be designed to withstand these high pressure loads. If the canister is not designed for all possible external loads combinations, structural defects such as plastic deformations, cracks, and buckling etc. may occur in the canister during depositing it in the deep repository. Therefore, various structural analyses must be performed to predict these structural problems like plastic deformations, cracks, and buckling. Structural safety evaluation criteria of the canister are studied and defined for the validity of the canister design prior to the structural analysis of the canister. And structural design requirements(variables) which affect the structural safety evaluation criteria should be discussed and defined clearly. Hence this paper presents the structural design requirements(variables) and safety evaluation criteria of the spent nuclear fuel disposal canister.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.4
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• pp.441-454
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• 2018

Since the permanent shutdown of Kori Unit 1 in 2017, a full-scale decommissioning project for a commercial nuclear reactor has been approaching. It is estimated that about 160,000 t of low-activity concrete waste will be produced from decommissioning of one unit of this commercial nuclear power reactor. Accordingly, it is necessary to review whether the effectiveness of the current regulatory framework for clearance waste (i.e. waste stream that meets activity concentration guidelines or dose criteria for clearance set forth in NSSC Notice No. 2017-65) can be maintained for the clearance of a bulk amount of concrete waste. In this regard, the IAEA SRS No. 44, which was used as a basis for revision of the Korean clearance regulations, is thoroughly analyzed and the radiological effects from four different clearance scenarios, along with input values and parameters derived from industrial practices in Korea, were evaluated. Though it is shown that the maximum annual dose from most recycling scenarios will be less than the clearance dose criterion for the normal scenario (i.e. an order of magnitude of $0.01mSv{\cdot}y^{-1}$), the radiation dose, estimated with conservative assumptions for the banking scenario, may exceed the above clearance dose criteria. Therefore, for safe and sustainable clearance of the bulk amount of concrete waste, it is required to diversify the concrete waste processors, perform more detailed site-specific assessment, and apply limiting conditions to the banking scenario.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.219-221
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• 2004

국가의 규제기관과 처분장에서는 방사성 폐기물의 안전한 영구처분을 위하여 폐기물 수용(인수)기준을 폐기물 발생자에게 준수토록 요구하게 되는데 이러한 폐기물 수용(인수)기준은 처분시설의 가동동안 인간과 환경 보호 그리고 최대 300년간의 제도적 통제기간을 고려하여 처분장의 안전성 확보를 위하여 설정되어진다. 폐기물 수용(인수)기준중 고화체의 안정성 평가와 관련하여 미국(NRC/BTP)은 폐기물의 종류와 고화매질에 따라 유리수, 압축강도, 방사성 조사특성, 미생물 영향 특성, 침수 및 침출 특성, 열순환 특성 등에 대하여 표준시험법을 제시하였으며, 또한 그의 기술기준치도 제시하고 있다. 그리고 프랑스(DRDD/ BECC)에서는 미국보다 매우 세밀하게 평가항목들을 분류하는 등의 처분장 운영국가에서는 고화체의 안정성관련 평가시험들을 처분 환경과 처분방식에 맞게 표준화하고 있다. 한편 국내에서는 과기부 고시 제2001-32호 "중.저준위 방사성폐기물 인도규정"이 있으나 이에는 고화체 관련하여 정성적인 안정성에 대하여서만 기술되어 있다. 이에 따라 원전폐기물 고화체에 대한 안정성 평가를 위한 시험법을 선정하기 위하여 아래 그림과 같은 절차에 따라 수행토록 하였다. 우선 대표적인 천층처분 운영국가인 미국과 프랑스의 시험법 그리고 IAEA 권고 시험법과 유사관련 한국 산업표준법들을 조사하고, 이들 시험법들의 주요 차이점을 기술적 관점에서 비교평가하고, 이어서 모의 방사성 및 비방사성 고화체를 이용하여 상기 시험법들을 각각 적용하고 또한 이들 시험법들간의 차이(시험 조건, 시편의 크기 등)에 기인한 상호 비교시험을 통하여 얻어진 시험결과들을 종합적으로 비교 검토하여 보수적 관점에서 시험법을 선정하는 것으로 방향을 잡았다. 이때 시험결과를 얻기 위한 모든 과정에 품질보증 활동을 적용키로 하였으며, 시험결과 분석/평가 과정과 시험법 선정에 각계(규제기관, 학계, 발전소 현장 및 산업계 등) 전문가로부터 기술자문회의를 통하여 자문 의견을 받기로 하였다. 특히 현재 폐기물 인수 기술기준치가 설정된 국가의 시험법을 심층 있게 검토하기로 하였다.검토하기로 하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.205-210
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• 2005

The proposed regulation for low and intermediate level radioactive waste disposal facility, scheduled to be revised, recommends that the waste generator should verify the radioactive waste conforms to the disposal requirements before disposing of it. According to the regulation, the radionuclide concentration of the radioactive waste, and its physical and chemical characteristics and safety must be confirmed prior to the disposal of low and intermediate level radioactive wastes, and the waste generator is required to deliver this information to the disposal facility operator. In addition, the disposal facility operator must assess the safety of the disposal site to establish the SWAC (Site Specific Waste Acceptance Criteria) in consideration of the characteristics of the site, whereas the waste generator must comply with the criteria in managing, disposing of and delivering low and intermediate level radioactive wastes. To abide by the afore-mentioned regulation and criteria, the waste generator must verify that the radioactive wastes to be disposed of are suitable for disposal before they are transported to the disposal facility, and to this end a radioactive waste certification program must be developed. This study conducted an in-depth analysis of the radioactive waste certification programs enforced in countries advanced in atomic energy to develop a draft of a certification program applicable to local power plants, and the program is currently applied as pilot to Uljin Power Plants No. 1 & 2 to prove its applicability. This study is going to analyze the results of the pilot application with a view to developing a radioactive waste certification program suitable to local conditions.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.237-237
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• 2004

사용후핵연료를 건식처리하여 핵연료성 물질을 제거하고 또한 장반감기 핵종을 제거하면 처분 대상의 폐기물이 남게 된다. 이 폐기물의 양을 줄이고 관리기간을 단축시키는 방안을 강구하는 것이 처분전에 수행하는 전처분(pre-disposal)의 주 목표이다. 처분후에는 건식처리된 과정과는 달리 장기적으로 관리하여야 하며, 물의 유입에 의한 침출 문제등 습식 환경도 고려하여야 한다. 따라서 궁극적으로 처분되어지는 폐기물에 대해서는 물의 영향을 파악하는 것이 필수적이다.(중략)