• Proceedings of the Korean Radioactive Waste Society Conference
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• 2015.10a
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• pp.201-202
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• 2015

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.05a
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• pp.289-290
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• 2016

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.06a
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• pp.126-127
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• 2006

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.11a
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• pp.147-148
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• 2007

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.2
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• pp.85-93
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• 2013

This study has been carried out to elucidate the characteristics of the dissolution for Thermal Decomposed Solid Waste of uranium-bearing sludge (TDSW), the removal of impurities by an alkalization in a nitric acid dissolving solution of TDSW, and the selective removal (/recovery) of uranium by an acidification in an carbonate alkali solution, respectively. TDSW generated by thermal decomposition of U-bearing sludge which was produced in the uranium conversion plant operation, was stored in KAERI as a solid-powder type. It is found that the dissolution of TDSW is more effective in nitric acid dissolution than oxidative-dissolution with carbonate. At 1 M nitric acid solution, TDSW was undissolved about 30wt% as a solid residue, and uranium contained in TDSW was dissolved more than 99%. In order to the alkalization for the nitric acid dissolving solution of TDSW, carbonate alkalization is more effective with respect to remove the impurities. At the carbonate alkali solution controlled to about 9 of pH, Al, Ca, Fe and Zn co-dissolved with U in dissolution step was removed about $98{\pm}1%$. On the other hand, U could be recovered more than 99% by an acidification at pH about 3 in a carbonate alkali solution, which was nearly removed the impurities, adding 0.5M $H_2O_2$. It was found that uranium could be selectively recovered (/removed) from TDSW.

• Nuclear industry
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• no.9_10 s.9
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• pp.41-43
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• 1982

방사성폐기물처리는 기술혁신의 시대를 맞이하고 있다. 역침투막기술등 날로 발전하고 있는 처리기술이 방사성폐기물처리분야에 응용되어 결실되어가고 있다. 이와같은 처리기술이 순조롭게 궤도에 오른다면, 장차 고체폐기물의 량은 현재의 10분의 1로 감소될 가능성도 있다. 이렇게 되면, 경우에 따라서는 내용년수 30년동안에 발생되는 폐기물은 모두 부지내에 저장하였다가 폐로시에 일괄하여 처리하는 것도 기술적으로 가능하여 진다고 하겠다. 여기서는 일본의 동경전력(주)을 예로 폐기물처리기술개발의 현상을 알아 본다.

• Proceedings of the Korea Air Pollution Research Association Conference
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• 2001.11a
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• pp.97-98
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• 2001

폐기물 소각로는 주입 폐기물의 성상이 균일하지 못하므로 폐기물의 불완전 연소에 의한 유해중간 생성물들이 생성되므로 논란이 되어왔다. 이를 제어하기 위해서는 공기량, 공기 주입방법, 공기 예열온도등에 운전조건들의 선정이 매우 중요하다. 이를 위해 진행되어온 연구는 크게 실험적 방법과 수치 해석적 방법의 두 범주로 나뉘어진다. 이에 본 연구에서는 수치해석적 방법으로 광주 상무신도심에 설치 가동중인 200톤/일 용량의 소각로내의 열유동 현상을 해석하기 위하여 고체 폐기물이 매우 빠르게 탈휘(devolatilization)되는 것으로 가정, 메탄가스로 단순화(Chen et al, 1999)하였다. (중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.141-148
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• 2003

A data collection of a liquid radioactive waste treatment process of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by treatment process. Data on the actual treatment process that is not limited experiment improve by a document, human traces, saving of material resources and improve with efficiency of tracking about a radioactive waste and a process and give help to radioactive waste material valance and inventory study.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.168-171
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• 2003

The IMEF(Irradiated Materials Examination Facility), located in KAERI site, is a hot cell facility to test and evaluate the irradiation defects or embrittlement through post-irradiation examination(PIEs) of irradiated nuclear fuels and structural materials which are come from HANARO research reactor and commercial nuclear power plants. Therefore, to carry out its own function, the high level solid radioactive wastes, produced through PIEs, are periodically carried out and managed from hot cell to monolith. So far, approximately 30 drums which contains 50 liters are transported to monolith, and it is shown that the quantity is slowly increasing, In this paper, the procedures and work contents of the high level solid radwaste carrying out and management for IMEF are described in detail.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 1993.05a
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• pp.116-119
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• 1993

고체연료의 연료특성을 완전히 파악하기는 어렵다. 하지만 기존의 알고있는 자료를 이용해서 고체연료의 연소특성을 예측할 수 있을 것이다. 그래서, 이미 어느 정도 알려져 있는 미분탄의 연소특성을 이용하여 폐기물의 연소특성을 예측하기 위해서 새로운 열중량 분석장치를 개발하게 되었으며, 여기에서는 그 개발절차 및 기초실험 결과를 실었다. 기초실험 결과 미소질량일 경우와 약간의 차이가 발견되었다. 그러나 그 개형은 기존의 자료들과 큰 차이가 없는 것으로 보여진다.