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Conceptual Designs and Evaluation of the Treatment Process of Square and Cylindrical Concrete Re-Package Drums KCI 등재 SCOPUS

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방사성폐기물학회지 (Journal of the Korean Radioactive Waste Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

After the permanent shut down of Kori Unit 1, various decommissioning activities will be implemented, including decontamination, segmentation, waste management, and site restoration. During the decommissioning period, waste management is among the most important activities to ensure that the process proceeds smoothly and within the expected timeframe. Furthermore, the radioactive waste generated during the operation should be sent to a disposal facility to complete the decommissioning project. Square and cylindrical concrete re-package drums were generated during the 1980s and 1990s. The square, containing boron concentrates, and cylindrical, containing spent resin, concrete re-package drums have been stored in a radioactive waste storage building. Homogeneous radioactive waste, including boron concentrates, spent resin, and sludge, should be solidified or packaged in high-integrity containers (HICs). This study investigates the sequential segmentation process for the separation of contaminated and non-contaminated regions, the re-packaging process of segmented or crushed cement-solidified boron concentrate, and re-packaging in HICs. The conceptual design evaluates the re-packaging plan for the segmented and crushed cement-solidified waste using HICs, which is acceptable in a disposal facility, and the quantity of generated HICs from the treatment process.

목차
1. Introduction
2. General Description of Square and CylindricalConcrete Re-Package Drums
    2.1 Square Concrete Re-Package Drums
    2.2 Cylindrical Concrete Re-Package Drums
3. Result and Discussion
    3.1 Pre-Treatment of Square and CylindricalConcrete Re-Package Drums
    3.2 Packaging of Radioactive Waste InnerDrums in HIC
4. Conclusion
Conflict of Interest
REFERENCES
저자
  • Young Hwan Hwang(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea) Corresponding author
  • Sunghoon Hong(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Seong-Sik Shin(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Seokju Hwang(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Jung-Kwon Son(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Cheon-Woo Kim(Central Research Institute, Korea Hydro & Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Changgyu Kim(Doosan Enerbility Co., Ltd., 22, Doosan volvo-ro, Seongsan-gu, Changwon-si, Gyeongsangnam-do 51711, Republic of Korea)
  • Kwang Soo Park(Doosan Enerbility Co., Ltd., 22, Doosan volvo-ro, Seongsan-gu, Changwon-si, Gyeongsangnam-do 51711, Republic of Korea)
  • Taeseob Lim(Doosan Enerbility Co., Ltd., 22, Doosan volvo-ro, Seongsan-gu, Changwon-si, Gyeongsangnam-do 51711, Republic of Korea)
  • Donghun Park(Doosan Enerbility Co., Ltd., 22, Doosan volvo-ro, Seongsan-gu, Changwon-si, Gyeongsangnam-do 51711, Republic of Korea)