• Title/Summary/Keyword: solidifying material for radioactive waste

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Analysis of Utilizing Recycled Cement Containing Calcium Phosphate as a Solidifying Material for Radioactive Waste Disposal (인산칼슘이 함유된 재생시멘트의 방사성 폐기물 고화재 활용성 검토)

  • Gong, Dong-Geon;Kim, Ji-Hyun;Chung, Chul-Woo
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2021.05a
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    • pp.191-192
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    • 2021
  • For the stable management of radioactive waste, it is necessary to secure a solidification treatment technology capable of immobilizing hazardous radioactive elements in a solid matrix. In this study, the feasibility of using recycled cement recovered from waste concrete as a solidifying material for radioactive waste was analyzed.

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Evaluation of Hydration Reactivity of Recycled Cement for the Utilization of Radioactive Waste Solidifying Materials (방사성 폐기물 고화재 활용을 위한 재생시멘트의 수화반응성 평가)

  • Choi, Yu-Jin;Kim, Ji-Hyun;Chung, Chul-Woo
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2022.11a
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    • pp.167-168
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    • 2022
  • Recently, starting with the permanent suspension of Gori 1 in Korea, the importance of the disposal of concrete structures in nuclear power plants has emerged, and environmental and safety are required to be proved accordingly. Safe radioactive waste disposal technology that immobilizes harmful radioactive elements, which are by-products of nuclear power, inside a solid matrix and recycling measures are needed to secure an efficient waste disposal space. This study was conducted to confirm whether recycled cement generated in the process of radioactive concrete treatment can be used as a solidifying material for radioactive waste treatment. In order to simulate the concrete exposed to radiation, aqueous solutions of Di-water, CsCl 1M, and CoCl2 1M were used as blending water at W/B 0.5. Tricalcium phosphate and Prussian blue were substituted with 5 wt.% based on the weight of recycled cement as a binder to improve solidification performance, and their hydration characteristic was analyzed.

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

  • Young Hwan Hwang;Mi-Hyun Lee;Seok-Ju Hwang;Jung-Kwon Son;Cheon-Woo Kim;Suknam Lim
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.3
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    • pp.411-417
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    • 2023
  • 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.