극저준위 콘크리트, 금속 해체방폐물의 방사선적 특성을 고려한 매립형처분시설 방사선작업자 예비 피폭선량 평가
Preliminary Radiation Exposure Dose Evaluation for Workers of the Landfill Disposal Facility Considering the Radiological Characteristics of Very Low Level Concrete and Metal Decommissioning Wastes
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초록
The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanentshutdown, is expected to generate a large amount of various types of radioactive waste during thedismantling process. For the disposal of Very-low-level waste, which is expected to account for thelargest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detaileddesign to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is beingdeveloped to efficiently dispose of metal and concrete waste, which are mainly generated as Very lowlevelwaste of decommissioning. In this study, based on the design characteristics of the 3-phaselandfill disposal facility and the large container under development, radiation exposure dose evaluationwas performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using theMCNP computer program, and the internal and external exposure dose evaluation due to damage tothe decommissioning waste package during a drop accident was performed based on the evaluationmethod of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determinewhether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of theevaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limitwas confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the largecontainer for dismantled radioactive waste, which is currently under development, was confirmed.
Abstract
The Kori Unit 1 nuclear power plant, which is planned to be dismantled after permanentshutdown, is expected to generate a large amount of various types of radioactive waste during thedismantling process. For the disposal of Very-low-level waste, which is expected to account for thelargest amount of generation, the Korea Radioactive waste Agency (KORAD) is in the process of detaileddesign to build a 3-phase landfill disposal facility in Gyeongju. In addition, a large container is beingdeveloped to efficiently dispose of metal and concrete waste, which are mainly generated as Very lowlevelwaste of decommissioning. In this study, based on the design characteristics of the 3-phaselandfill disposal facility and the large container under development, radiation exposure dose evaluationwas performed considering the normal and accident scenarios of radiation workers during operation. The direct exposure dose evaluation of workers during normal operation was performed using theMCNP computer program, and the internal and external exposure dose evaluation due to damage tothe decommissioning waste package during a drop accident was performed based on the evaluationmethod of ICRP. For the assumed scenario, the exposure dose of worker was calculated to determinewhether the exposure dose standards in the domestic nuclear safety act were satisfied. As a result of theevaluation, it was confirmed that the result was quite low, and the result that satisfied the standard limitwas confirmed, and the radiational disposal suitability for the 3-phase landfill disposal facility of the largecontainer for dismantled radioactive waste, which is currently under development, was confirmed.
참고문헌 (19)
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