• 한국건설순환자원학회논문집
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• 제6권2호
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• pp.74-80
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• 2011

본 연구에서는 대표적인 콘크리트용 산업부산자원인 플라이애쉬와 고로슬래그미분말을 교량 덧씌우기용 고성능 콘크리트에 적용하기 위하여 배합조건별 역학특성과 자기수축 특성 및 내염특성을 평가하였으며, 평가결과 수경성 광물질 혼화재의 혼합사용은 염분과 알칼리 골재 반응에 대한 저항성 개선효과로 내구성 증진에 크게 기여하고 자기수축 변형에 대한 저항성 개선에도 효과가 있는 것으로 나타났다. 이 고성능 콘크리트는 재료와 시공 측면에서 내구성과 효율성을 개선시킨 콘크리트로서 폐자원의 활용으로 인한 친환경, 경제성까지 확보할 수 있을 것으로 사료된다.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2012년도 추계 학술논문 발표대회
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• pp.61-62
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• 2012

This study is for analyzing possibility of utilizing as cement from waste concrete. The scrapped fine powder which contains a large amount of hydrate of cement can supercede lime stone, and greenhouse gas reductions are expected. However, Fine Aggregate powder efficient separation technology development is essential for that limestone substitution effect and reduce greenhouse gas emissions in order to facilitate through the recycling of the scrapped fine powders.

• 한국세라믹학회지
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• 제47권5호
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• pp.419-425
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• 2010

In order to examine the P.H.C pile raw material using glass forming ceramic. The used materials is ordinary portland cement, waste TFT-LCD glass powder and reactive agent(Ca$(OH)_2$). The first experiment is characteristics analysis of the waste TFT-LCD glass powder, For the second experiment is mortar and concrete compressive strength for using of the concrete file raw material for waste TFT-LCD glass powder. The results of experiment showed that the substitution ratio of 10% waste TFT-LCD glass powder and 1% reactive agent(Ca$(OH)_2$) was excellent at a point of view for the physical characteristic. The study's most important finding is that the recycling of waste TFT-LCD glass powder.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2023년도 봄 학술논문 발표대회
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• pp.305-306
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• 2023

Recently, as the radioactive waste disposal facility becomes scarce, the importance of efficient disposal of waste from nuclear power plants is increasing. This study was conducted to utilize radioactive waste concrete powder as solidifying agent for radioactive waste treatment. Paste with an age of more than one year was used with a disk mill to have a particle size of 150㎛ or less, and treated at temperatures of 500℃, 600℃ and 700℃ for 2 hours. In order to simulate the radioactive cement powder, aqueous solutions of Di-water, CsCl 1M, SrCl₂ 1M and CoCl₂ 1M were used as blending water at W/C 0.7 and to improve fluidity, polycarboxylate type superplasticizer was used at 0.4 wt.% based on the weight of recycled cement paste powder. Characterisation was carried out using vicat method, strength and density.