Evaluation of Hydration Reactivity of Recycled Cement for the Utilization of Radioactive Waste Solidifying Materials

방사성 폐기물 고화재 활용을 위한 재생시멘트의 수화반응성 평가

  • 최유진 (부경대학교, 건축.소방공학부) ;
  • 김지현 (부경대학교, 융복합인프라기술연구소) ;
  • 정철우 (부경대학교, 건축공학과)
  • Published : 2022.11.10

Abstract

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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Acknowledgement

본 연구는 2020년도 산업통상자원부의 재원으로 한국에너지기술평가원(KETEP)의 지원을 받아 수행한 연구과제입니다(No.20203210100150).