RESRAD-RECYCLE 전산코드를 활용한 금속폐기물 내 우라늄 자체처분허용농도 예비 평가
Preliminary Evaluation of Clearance Level of Uranium in Metal Waste Using the RESRAD-RECYCLE Code
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참고문헌
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초록
The clearance level by nuclide is announced by the Nuclear Safety and Security Commission. However, the clearance level of uranium existing in nature has not been announced, and research isneeded. Therefore, the purpose of this study was to evaluate the clearance level of uranium nuclidesappropriate to domestic conditions preliminary. For this purpose, this study selected major processes forrecycling metal wastes and analyzed the exposure scenarios and major input factors by investigating thecharacteristics of each process. Then, the radiation dose to the general public and workers was evaluatedaccording to the selected scenarios. Finally, the results of the radiation dose per unit radioactivity foreach scenario were analyzed to derive the clearance level of uranium in metal waste. The results of theradiation dose assessment for both the general public and workers per unit radioactivity of uraniumisotopes were shown to meet the allowable dose (individual dose of 10 μSv y-1 and collective dose of 1Man-Sv y-1) regulated by the Nuclear Safety and Security Commission. The most conservative scenariosfor volumetric and surface contamination were evaluated for the handling of the slag generated after themelting of the metal waste and the direct reuse of the contaminated metal waste into the building withoutfurther disposal. For each of these scenarios, the radioactivity concentration by uranium isotope wascalculated, and the clearance level of uranium in metal waste was calculated through the radioactivityratio by enrichment. The results of this study can be used as a basic data for defining the clearance levelof uranium-contaminated radioactive waste.
Abstract
The clearance level by nuclide is announced by the Nuclear Safety and Security Commission. However, the clearance level of uranium existing in nature has not been announced, and research isneeded. Therefore, the purpose of this study was to evaluate the clearance level of uranium nuclidesappropriate to domestic conditions preliminary. For this purpose, this study selected major processes forrecycling metal wastes and analyzed the exposure scenarios and major input factors by investigating thecharacteristics of each process. Then, the radiation dose to the general public and workers was evaluatedaccording to the selected scenarios. Finally, the results of the radiation dose per unit radioactivity foreach scenario were analyzed to derive the clearance level of uranium in metal waste. The results of theradiation dose assessment for both the general public and workers per unit radioactivity of uraniumisotopes were shown to meet the allowable dose (individual dose of 10 μSv y-1 and collective dose of 1Man-Sv y-1) regulated by the Nuclear Safety and Security Commission. The most conservative scenariosfor volumetric and surface contamination were evaluated for the handling of the slag generated after themelting of the metal waste and the direct reuse of the contaminated metal waste into the building withoutfurther disposal. For each of these scenarios, the radioactivity concentration by uranium isotope wascalculated, and the clearance level of uranium in metal waste was calculated through the radioactivityratio by enrichment. The results of this study can be used as a basic data for defining the clearance levelof uranium-contaminated radioactive waste.
참고문헌 (22)
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