Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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A Study on the Construction of Cutting Scenario for Kori Unit 1 Bio-shield considering ALARA

  • Hak-Yun Lee (Department of Nuclear Engineering, Chosun University) ;
  • Min-Ho Lee (Department of Nuclear Engineering, Chosun University) ;
  • Ki-Tae Yang (Department of Nuclear Engineering, Chosun University) ;
  • Jun-Yeol An (Department of Nuclear Engineering, Chosun University) ;
  • Jong-Soon Song (Department of Nuclear Engineering, Chosun University)
  • Received : 2023.05.10
  • Accepted : 2023.07.28
  • Published : 2023.11.25
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Abstract

Nuclear power plants are subjected to various processes during decommissioning, including cutting, decontamination, disposal, and treatment. The cutting of massive bio-shields is a significant step in the decommissioning process. Cutting is performed near the target structure, and during this process, workers are exposed to potential radioactive elements. However, studies considering worker exposure management during such cutting operations are limited. Furthermore, dismantling a nuclear power plant under certain circumstances may result in the unnecessary radiation exposure of workers and an increase in secondary waste generation. In this study, a cutting scenario was formulated considering the bio-shield as a representative structure. The specifications of a standard South Korean radioactive waste disposal drum were used as the basic conditions. Additionally, we explored the hot-to-cold and cold-to-hot methods, with and without the application of polishing during decontamination. For evaluating various scenarios, different cutting time points up to 30 years after permanent shutdown were considered, and cutting speeds of 1-10nullm2/h were applied to account for the variability and uncertainty attributable to the design output and specifications. The obtained results provide fundamental guidelines for establishing cutting methods suitable for large structures.

Keywords

Acknowledgement

This study was supported by the Nuclear Power Core Technology Development Program of the Korea Institute of Energy Technology Evaluation and Planning (KETEP),granted financial resource from the Ministry of Trade, Industry & Energy, Republic of Korea. (No.20191510301120). This work was supported by the Korea Institute of Energy Technology Evaluation and Planning, and the Ministry of Trade, Industry and Energy of the Republic of Korea (No. 20201510300130).

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