Occupational radiation doses to workers handling linkage management equipment for spent nuclear fuel at interim storage facility
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초록
When managing SNF according to the management stages, if the interchangeability between the transport and storage systems is not considered, inefficient trial-and-error can occur. The metal overpack is a cask that utilizes the DPC to transport and store SNF, and is a linkage management equipment that enhances the interchangeability between management stages. The purpose of this study is to assess a radiation dose for workers handling linkage management equipment in an interim storage facility. For this purpose, radiation exposure scenarios for workers handling linkage management equipment were set. Then, using Monte Carlo computer code, radiation dose rates were calculated for each work location. Finally, total dose and individual dose were calculated for each work. The radiation exposure scenarios for workers were categorized into storage and transportation work. Each work was composed of 16 and 13 tasks. The total radiation dose calculation for the handling linkage management equipment in the interim storage facility for a single DPC showed that storage workers and transportation workers exposed to total 2.144 man-mSv and 1.877 man-mSv, respectively. The results of this study can be used for the development of safety linkage management technologies between the stages of SNF management in the future.
Abstract
When managing SNF according to the management stages, if the interchangeability between the transport and storage systems is not considered, inefficient trial-and-error can occur. The metal overpack is a cask that utilizes the DPC to transport and store SNF, and is a linkage management equipment that enhances the interchangeability between management stages. The purpose of this study is to assess a radiation dose for workers handling linkage management equipment in an interim storage facility. For this purpose, radiation exposure scenarios for workers handling linkage management equipment were set. Then, using Monte Carlo computer code, radiation dose rates were calculated for each work location. Finally, total dose and individual dose were calculated for each work. The radiation exposure scenarios for workers were categorized into storage and transportation work. Each work was composed of 16 and 13 tasks. The total radiation dose calculation for the handling linkage management equipment in the interim storage facility for a single DPC showed that storage workers and transportation workers exposed to total 2.144 man-mSv and 1.877 man-mSv, respectively. The results of this study can be used for the development of safety linkage management technologies between the stages of SNF management in the future.