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A Study on Cutting Technology for Dismantling Metal Structures of Nuclear Power Plant

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

Currently, dismantling technology for decommissioning nuclear power plants is being developed around the world. This study describes the cutting technology and one of the technologies being considered for the RV/RVI cutting of Kori Unit 1. The dismantling technology for nuclear power plants include mechanical and thermal methods. Mechanical cutting methods include milling, drill saw, and wire cutting. The advantages of the mechanical method are less generating aerosol and less performance degradation in water. However, the cutting speed is slow and the reaction force is large. Thermal cutting methods use heat sources such as plasma arcs, oxygen, and lasers. The advantages of thermal method are fast cutting speed, low reaction force and thick material cutting. On the other hand, they have problems with fume and melt. Among them, the cutability of the oxygen cutting method is better in carbon steel than in stainless steel. In order to cut the RV/RVI of the Kori Unit 1, the applicability of fine plasma, arc saw, and band/ wheel saw is being reviewed. For RV cutting, the applicability of arc saw and oxy-propane is being considered Because RV is mostly made of carbon steel. However, since the flange is cladded with stainless steel, the use of mechanical methods such as wire saws should be considered. In the case of RVI, since it has a complicated shape and is made of stainless steel, it seems necessary to review various cutting methods. In addition, it will be necessary to minimize radiation exposure of workers by cutting underwater cutting.

저자
  • Jeongsu Jeong(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon)
  • Sunghoon Hong(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon)
  • Seoyong Choi(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon)
  • Mingyu Choi(Central Research Institute, Korea Hydro & Nuclear Power Company Limited, 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon) Corresponding author