• Title/Summary/Keyword: 금속폐기물고화체

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Post Process Associated with the Electrochemical Reduction Process - Smelting of a Metal Product and Solidification of a Molten Salt (전해환원공정 관련 후처리공정 - 금속전환체 Smelting 및 용융염 고화)

  • 허진목;정명수;이원경;조수행;서중석;박성원
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.278-284
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    • 2004

  • The processes for the smelting of a metal product and the solidification of a molten salt were developed respectively to treat the products from the electrochemical reduction process. The method for the separation of a metal product in a magnesia container from the residual. salt and consequent smelting of it to a metal ingot by the multi step heating in vacuum was proposed. The new concept using a dual vessel and a salt valve was also suggested for the solidification of a molten salt into a regular size and shape which is suitable for the transport and measurement. The results obtained in the study will be applied to the design of the hot cell demonstration system of the Advanced Spent Fuel Conditioning Process of KAERI.

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방사성 소각재 함유 고화체의 매질 조성이 용출특성에 미치는 영향에 관한 연구

  • 김광종;이규성;정찬우;김인태;김준형;서용칠
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.186-190
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    • 2003

  • 유리고화체의 내구성과 조성에 관한 이 연구의 목적은 구조적 모델, 비가교 산소 모델(NBO) 및 간단한 경험적 모델(Valence-oxygen)과 함에 침출실험결과들을 비교하는 것이다. 조성에 기초한 모델들 사이의 연관성들은 이와 같은 모델들이 지질학적 유리와 제조된 유리의 관련성에 대해 유리고화체의 내구성을 설명할 수 있다는 것을 나타낸다 이러한 관계는 유리고화체의 장기간 내구성을 결정하는데 도움을 줄 수 있으며, 모델을 통한 유리고화체의 조성에 의한 실험결과에의 영향성을 검토하였다 9$0^{\circ}C$에서 7일간 수행된 PCT 침출시험을 대상으로 모델들을 비교하였으며 Ash Loading wt%가 증가할수록 망목형성이온이 증가하기 때문에 침출농도 및 침출분율이 감소하는 것을 확인 할 수 있었으며, VO model의 변수 값이 증가할수록 주요 유리매질의 침출분율은 완만한 기울기를 가지며 감소하다. 금속류의 침출분율은 VO model의 변수 값이 감소함에 따라 대체적으로 증가함을 확인 할 수 있었다.

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Development on Glass Formulation for Aluminum Metal and Glass Fiber (유리섬유 및 알루미늄 금속 혼합물 유리조성 개발)

  • Cho, Hyun-Je;Kim, Cheon-Woo
    • 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.

  • https://doi.org/10.7733/jkrws.2012.10.4.247 인용 PDF KSCI

Leaching Characteristic Analysis of Cement Solidified Radioactive Waste Attached by Yellow Sand Rain (황사빗물의 영향에 의한 방사성 폐기물 시멘트 고화체의 침출특성 분석)

  • 김혜진;이수홍;황주호;이재민
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2003.11a
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    • pp.244-250
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    • 2003

  • With a recent public concern rising on the radioactive waste, it is disclosed that the problem is more serious than expected. This research has been conducted to find effects of yellow sandy rainwaters on the solidified cement of mid-and-low level radioactive waste. The ANS 16.1 standard test method was chosen for this leaching experiment. Make a cement solidified radioactive waste that contains Co nuclide, and fabricate it for over 28 days. Then, decide on the volume of leaching water and the concentration of ion and metal in leachate from the mass concentration of yellow sands in atmosphere. In this paper, we have taken a short look at characteristics of yellow sand. Before going into the leaching experiment, we decided experimental conditions first. Then, it was evaluated and analyzed how sandy rainfalls have impact on the cement solidified radioactive waste based on data from 90 days of leaching experiment.

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