• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.211-212
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• 2012

• Korean Journal of Materials Research
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• v.5 no.3
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• pp.288-296
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• 1995

본 연구에서는 석재공장 주변의 오염원으로 되고 있는 화강암 폐재의 고화체의 형성과 평가 기술에 관한 내용을 다루었다. 이를 위해, 최근 고화체의 함성기술로서 높이 평가받고 있는 수열 Hot press법을 이용하여 분말형태의 화강암 폐기물을 고화시키는데 필요한 조건을 찾아내었다. 아울러 고화체의 기계적 성질과 파면의 양상 및 수열실험동안 발생된 생성물 사이의 상호 관계를 고찰하였다. 고화체의 기계적 성질은 수열실험조건에 의존성이 있었으며, 적절한 고화조건은 반응온도 30$0^{\circ}C$, 유지시간 1시간이었다. 또한 고화체의 파면은 반응온도 및 유지시간에 따라 현저히 다른 양상을 보였으며, 수열실험동안 다양한 화합물이 생성되었다. 그 중에서 Xonotlite와 Talc는 고화체의 강도를 저하시키는 주된 화합물이었다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.05a
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• pp.81-82
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.118-119
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• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.05a
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• pp.373-374
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• 2016

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2012.05a
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• pp.169-170
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• 2012

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.4
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• pp.247-254
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• 2012

Vitrification technology has been widely applied as one of effective processing methods for wastes generated in nuclear power plants. The advantage of vitrifying for low- and intermediate-level radioactive wastes has a large volume reduction and good durability for the final products. Recently, a filter using on HVAC(Heating Ventilating & Air Conditioning System) is composed with media (glass fiber) and separator (aluminum film) has been studied the proper treatment technology for meeting the waste disposal requirement. Present paper is a feasibility study for the filter vitrification that developing of the glass compositions for filter melting and melting test for physicochemical characteristic evaluation. The aluminum metal of film type is preparing with 0.5 cm size for proper mixing with glass frit, glass fiber is also preparing with 1 cm size within crucible. The glass compositions should be developed considering molten glass are related with wastes reduction. Glass compositions obtained from developing on glass formulation are mainly composed of $SiO_2$ and $B_2O_3$ for aluminum metal. A variety of factors obtained from the glass formulation and melting test are reviewed, which is feeding rate and glass characteristics of final products such as durability for implementing the wastes disposal requirement.

• Journal of the Korea Institute of Building Construction
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• v.17 no.3
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• pp.269-277
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• 2017

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.

• Nuclear Engineering and Technology
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• v.23 no.1
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• pp.81-94
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• 1991

In order to develop the acceptance criteria for the low and intermediate level radioactive wastes for the land disposal: the following items were reviewed : classifications of radioactive wastes is respect to disposal, basic requirements and criteria that have to be considered during waste management from the origin to disposal. From these studies, the standard test methods to evaluate radioactive waste forms（or packages) were shown.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.1
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• pp.49-56
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• 2010

In the pyroprocessing of spent nuclear fuels, LiCl-KCl waste salt containing radioactive rare earth chlorides are generated. The radioactive rare earth oxides are recovered by co-oxidative precipitation of rare earth elements. The powder phase of rare eath oxide waste must be immobilized to produce a monolithic wasteform suitable for storage and ultimate disposal. The immobilization of these waste developed in this study involves a solid state sintering of the waste with host borosilicate glass and zinc titanate based ceramic matrix(ZIT). And the rare-earth monazite which synthesised by reaction of ammonium di-hydrogen phosphate with the rare earth oxides waste, were immobilzed with the borosilicate glass. It is shown that the developed ZIT ceramic wasteform is highly resistant the leaching process, high density and thermal conductivity.