국내·외 원자력시설 부지 내 방사성폐기물 처리시설 현황 분석

김혁재; 라현준; 김기훈; 서현수; 김광표

doi:10.23042/radin.2022.16.2.151

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자료유형: 학술저널

저자정보: 김혁재 (경희대학교 원자력공학과) 라현준 (경희대학교 원자력공학과) 김기훈 (경희대학교 원자력공학과) 서현수 (경희대학교 원자력공학과) 김광표 (경희대학교)

저널정보: 한국방사선산업학회 방사선산업학회지 방사선산업학회지 제16권 제2호

발행연도: 2022.6

수록면: 151 - 160 (10page)

DOI: 10.23042/radin.2022.16.2.151

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When disposing of radioactive waste, the treatment must be preceded to reduce the amountof radioactive waste and retain the safety of disposal. Currently, many nuclear power plants in Koreaare about to be shut-down, and accordingly, large amounts of low- and intermediate- level waste areexpected to be generated due to decommissioning in the future. Because there are limits to treating allthose wastes through nuclear power plant radioactive waste management system, it is necessary toestablish an on-site radioactive waste treatment facility as an alternative. To establish on-site treatmentfacility, the investigation of on-site treatment process and related equipment must be preceded. Thepurpose of this study is to investigate the status of on-site radioactive waste treatment facilities indomestic and foreign nuclear facility. We selected on-site radioactive waste treatment facilities ofGermany’s Greifswald Nuclear Power Plant, Sweden’s Oskarshamn Nuclear Power Plant, Finland’sLoviisa Nuclear Power Plant, Japan’s Nuclear Science Research Institute, and the Korea Atomic EnergyResearch Institute as facilities to be investigated. As a result of analyzing the major treatment processesof on-site treatment facilities at domestic and foreign nuclear facilities, there were ten major treatmentprocesses in the facility, including measurement for clearance, compression, cutting, decontamination,incineration, melting, vaporization, and evaporation. Germany’s Greifswald nuclear power plant,Sweden’s Oskarshamn nuclear power plant, and Finland’s Loviisa nuclear power plant consideredtreatment of operational and decommissioning waste. In the case of decommissioning is beingperformed, decontamination treatment is being carried out. On-site treatment facilities of all nuclearpower plant were not considering evaporation, and that treatment process was performed only at theJapan Nuclear Science Research Institute and the Korea Atomic Energy Research Institute. As a resultof the analysis of the equipment utilized in the treatment facility, equipment for treatment is differentdepending on the treatment process of radioactive waste. In the case of cutting and decontamination,relatively flexible treatment equipment could be selected. Because the matrix for solidification isdetermined differently according to the characteristics of radioactive waste, the solidification treatmentequipment utilized by each treatment facility were different. The results of this study can be used as basicdata when establishing on-site radioactive waste treatment facility in the future.

#Low- and intermediate- level waste #On-site treatment facility #Treatment process #Treatment equipment

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