• Proceedings of the Korean Institute of Resources Recycling Conference
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• 2006.05a
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• pp.150-155
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• 2006

제강공정에서 발생되는 $CaO-Al_{2}O_{3}-SiO_{2}$계 조성을 갖는 2 차 정련슬래그 (래들 슬래그)를 이용하여 하수슬러지용 고화재개발 및 하수슬러지 고화체의 물성에 관한 연구를 수행하였다. 래들슬래그는 냉각과정에서 분화되는 성질이 있어 냉각후 분말상의 슬래그가 만들어진다. 분말상 슬래그의 주 결정상은 $12CaO{\cdot}7Al_{2}O_{3}$ 및 $2CaO{\cdot}SiO_{2}$로 구성되어 있다. $12CaO{\cdot}7Al_{2}O_{3}$ 상은 속경성 시멘트의 특징이 있다. 또한 $CaSO_{4}$와 혼합사용시 ettringite 상을 형성시켜 하수슬러지의 함수율 저감효과 및 강도발현 효과가 우수한 결과를 얻었다. $Cl^{-}$ 이온의 고정화면에서는 고화재중 래들슬래그의 혼합비가 높을수록 고화체 구조내에 $Cl^{-}$ 이온이 고정화되어 용출량은 감소하였다. 고화재로서 제강부산물을 사용하기 때문에 경제성이 있으며, $Cl^{-}$ 이온 함량이 높은 하수슬러지 고화재로서의 재활용이 기대된다.

• Applied Chemistry for Engineering
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• v.17 no.4
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• pp.391-396
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• 2006

When radioactive wastewater was solidified treatment by cement, the drying rate of cement and the volume reduction ratio was decreased because of boric acid component in the wastewater. In order to supplement the demerit, effects of paraffin wax investigated in this study. Paraffin wax has a hydrophobic properties and a low affinity with inorganic materials. When the radioactive wastewater was tested by a small of wax, the compressive strength of solidified waste are decreased Therefore boric acid in radioactive wastewater are first treated by alkali salt and coated by the stearic acid. During the solidification step, The amount of paraffin wax addition get the result that the compressive strength of solidification with cement was the same as that with paraffin wax. The leaching properties of radioactive waste solidified was the same CFL (cumulative fraction leached), PR (penetration rate), effective diffusivity if paraffin wax content in solidified waste was 20% or 25%.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.1 no.1
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• pp.41-46
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• 2003

To understand the long-term leach behavior of a borosilicate Waste glass in a repository, the leaching experiment with three kinds of simulated borosilicate waste glasses has been carried out since the middle of 1997. The five years results indicate that a boron would be applied as an indicator of a long-term leaching of their borosilicate waste glasses and that their long-term leach rates have a tendency to be close to about 0.03g/$m^2$-day even though their compositions and their ratios of the surface area to the volume of leachate are different.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.270.1-270
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• 2001

• Journal of the Korea Concrete Institute
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• v.25 no.3
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• pp.321-329
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• 2013

Recently, the medium-low level radioactive waste from nuclear power plant must be transported from temporary storage to the final repository. Medium-low level radioactive waste, which is composed mainly of the liquid ion exchange resin, has been consolidated with cementitious material in the plastic or iron container. Since cementitious material is brittle, it would generate cracks by impact load during transportation, signifying leakage of radioactive ray. In order to design the safety transporting equipment, there is a need to check the compressive strength of the current waste. However, because it is impossible to measure strength by direct method due to leakage of radioactive ray, we will estimate the strength indirectly by the dynamic modulus of elasticity. Therefore, it must be identified the relationship between of strength and dynamic modulus of elasticity. According to the waste acceptance criteria, the compressive strength of cement based solid is defined as more than 3.44 MPa (500 psi). Compressive strength of the present solid is likely to be significantly higher than this baseline because of continuous hydration of cement during long period. On this background, we have tried to produce the specimens of the 28 day's compressive strength of 3 to 30 MPa having the same material composition as the solid product for the medium-low level radioactive waste, and analyze the relationship between the strength and the dynamic modulus of elasticity. By controling the addition rates of AE agent, we made the mixture containing the ion exchange resin and showing the target compressive strength (3~30 MPa). The dynamic modulus of elasticity of this mixtures is 4.1~10.2 GPa, about 20 GPa lower in the equivalent compressive strength level than that of ordinary concrete, and increasing the discrepancy according to increase strength. The compressive strength and the dynamic modulus of elasticity show the liner relationship.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.367-372
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• 1996

석탄화력발전소의 산업부산물인 fly ash를 이용한 폐흡착재의 붕규산유리고화가 능성을 분석하였다. 폐흡착재는 기체상의 세슘이나 루테늄 등을 포집한 후에 발생되는 필터류 등의 고체폐기물을 말하며 본 실험에서는 CsNO$_3$와 fly ash를 몰비로 1.5 : 1 되게 섞어 1200 $^{\circ}C$에서 1시간 가소 시킨 후에 생성되는 pollucite를 모의폐흡 착재로 사용하였다. 폐흡착재를 무게비 15 ~ 30 %로 fly ash, SiO$_2$, $Na_2$CO$_3$, B$_2$O$_3$와 혼합한 후 1150 $^{\circ}C$에서 3시간 용융시켜 붕규산유리화시켰다. 제조된 붕규산유리고화체의 침출성을 평가하기 위하여 2일동안의 soxhlet 침출실험을 수행하였다. 한편 폐흡착재의 붕규산유리고화과정을 알아보기 위하여 붕규산유리고화체의 원료물질에 대하여 유리화과정과 동일한 조건하에서 TG/DTA분석을 수행하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.180-185
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• 2003

The reductions in final waste form and material costs, which were induced from an introduction of salt waste regeneration system, have been estimated and compared with those of the present pyrochemical process, which is under development in KAERI. The results calculated on the basis of published data and proper assumption showed that the final waste form of LiCl waste from the Advanced Conditioning Process would be reduced about 3.7 to#ton HM (from 5.4 to 1.7 ton/ton HM). For the case of LiCl-KCl eutectic salt waste from the electro-refining process, the final waste form would be reduced 2.3 ton/ton U. Thus, these estimation suggested that the introduction of salt waste regeneration system was essential to improve the economical efficiency of the pyrochemical process.

• Proceedings of the Korean Institute of Resources Recycling Conference
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• 2005.10a
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• pp.355-359
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• 2005

본 연구에서는 OPC 및 hauyne 클링커의 비산재에 대한 고화특성을 검토하였다. 비산재에 대해 OPC 및 OPC에 hauyne 클링커를 20%까지 대체하였을 때의 압축강도, 길이변화율, 중금속 용출량 등을 조사하였다. 결과로서, hauyne 클링커의 첨가량에 따라 고화체의 압축 강도가 증가하였다. hauyne 클링커의 첨가량은 10%내외가 적합하였으며, 그 이상에서는 길이변화율이 증가하며 팽창하였다. 고화체의 중금속 용출시험결과 모든 배합조건에서 환경기준치이하의 값을 나타내었다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.200-201
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• 2009

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.11a
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• pp.121-122
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• 2007