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Recycling Waste Paste from Concrete for Solidifying Agent

콘크리트 폐기물에서 분리된 페이스트를 활용한 고화재 기술개발 기초연구

  • Received : 2017.03.28
  • Accepted : 2017.05.24
  • Published : 2017.06.20

Abstract

In this work, as a preliminary experimental works, which focuses on utilizing separated pastes from activated (or radioactive) concrete as solidifying agents for radioactive waste immobilization, were performed. It was found that density of hydrated cement paste, which was lower than that of ordinary portland cement, increased as temperature for heat treatment increased. Highest compressive strength was observed with the specimens that was heat treated at $600^{\circ}C$. However, heat treatment over $700^{\circ}C$ showed higher CaO content that caused higher heat of hydration after in contact with water, lows of workability, and lower strength. Based on experimental results, it is suggested that $600^{\circ}C$ heat treatment is more appropriate for waste cement paste to be used as a solidifying agent.

본 연구에서는 원전 콘크리트로부터 분리된 페이스트 미분말을 이용 방사성폐기물 처분용 고화재로 활용하기 위하여 기초 특성을 검토하고자 하였다. 실험 결과 수화반응한 페이스트는 시멘트보다 비중이 낮고 수화회복을 위한 소성과정에서 온도증가에 따라 비중이 다르게 나타나 그에 따른 부피도 고려되어야 할 것으로 판단된다. 수화회복을 위한 소성온도에서 압축강도가 가장 우수한 온도조건은 $600^{\circ}C$로 나타났으며, $700^{\circ}C$ 이상에서는 CaO의 생성량이 과도하여 높은 수화열, 유동성 저하 및 낮은 강도가 발현되는 것을 확인하였다. 따라서 본 연구 범위 내에서 고화재로 활용 가능한 적정 수화회복 온도는 $600^{\circ}C$로 판단되며 폐콘크리트 페이스트가 적정한 열처리를 거치는 경우 방사성 폐기물 고화재료로서 활용될 수 있는 가능성을 보였다는 점에 의의를 둔다.

Keywords

References

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