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A Study on the Long-Term Integrity of Polymer Concrete for High Integrity Containers KCI 등재 SCOPUS

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

During the operation of a nuclear power plant (NPP), the generation of radioactive waste, including dry active waste (DAW), concentrates, spent resin, and filters, mandates the implementation of appropriate disposal methods to adhere to Korea’s waste acceptance criteria (WAC). In this context, this study investigates the potential use of polymer concrete (PC) as a high-integrity container (HIC) material for solidifying and packaging these waste materials. PC is a versatile composite material comprising binding polymers, aggregates, and additives, known for its exceptional strength and chemical stability. A comprehensive analysis of PC’s long-term integrity was conducted in this study. First, its compressive strength, which is crucial for ensuring the structural stability of HICs over extended periods, was evaluated. Subsequently, the resilience of PC was tested under various stress conditions, including biological, radiological, thermal, and chemical stressors. The findings of this study indicate that PC exhibits remarkable long-term properties, demonstrating exceptional stability even when subjected to diverse stressors. The results therefore underscore the potential viability of PC as a reliable material for constructing high-integrity containers, thus contributing to the safe and sustainable management of radioactive waste in NPPs.

목차
1. Introduction
2. Methods
    2.1 Mechanical Long-Term Stability: CreepTest
    2.2 Biological Stability
    2.3 Radiological Stability
    2.4 Freeze-thaw (Thermal Cycle) Stability
    2.5 Chemical Stability
3. Results and Discussions
    3.1 Basic Properties of Polymer Concrete
    3.2 Mechanical Long-Term Stability: CreepTest
    3.3 Biological Stability
    3.4 Radiological Stability
    3.5 Thermal Stability
    3.6 Chemical Stability
4. Conclusion
Conflict of Interest
저자
  • Young Hwan Hwang(Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea) Corresponding Author
  • Mi-Hyun Lee(Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Seok-Ju Hwang(Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Jung-Kwon Son(Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Cheon-Woo Kim(Central Research Institute, Korea Hydro and Nuclear Power Co., Ltd., 70, Yuseong-daero 1312beon-gil, Yuseong-gu, Daejeon 34101, Republic of Korea)
  • Suknam Lim(Kyelim polycon, 66, Gangnam-daero 30-gil, Seocho-gu, Seoul 06741, Republic of Korea)