• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.220-225
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• 2003

Generally, liquid radioactive wastes generated in nuclear power plant exist in powder form which do not contain moisture through the evaporating process of the Liquid Waste Management System and drying process of the Concentrated Waste Drying System. This powder form wastes are blended homogeneously with paraffin solidification agent and packed in metal drum to ensure its stability during handling and disposal. However, it was experienced that the powder form wastes were not blended homogeneously and separated into two layers in metal drum, on the other hand, a Portion of powder was adhered and solidified to the Inside parts of facility during the blending process. And the flaw of blending process above would come in case the mole ratio of Boron to Sodium in liquid radioactive wastes exceeds 0.2.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.4
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• pp.297-308
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• 2007

The granulation equipment of concentrated wastes is manufactured for the polymer solidification of concentrated wastes. It uses liquid sodium silicate as a granulating agent for the granulating of dried powder containing boric acid. The granulating agent is sprayed in the form of droplet and mean size of dried granules is $2{\sim}4mm$. The new technology which has been used for the polymer solidification of spent resin in U.S. and certified by Nuclear Regulatory Commission (NRC) is successfully applied to concentrated wastes. This uses in-situ solidification process within drum without mechanical mixing. Maximum loading of waste can be achieved without increasing of waste volume. Polymer waste forms were evaluated with several test such as fire test, compressive strength test, leaching test, immersion test, irradiation test, and thermal cycling test according to standard test procedures.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.2
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• pp.143-150
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• 2010

Vitrification technology has been gradually recognized as one of effective solidification methods for concentrated boric acid wastes generated in PWR. Vitrification for low- and intermediate-level radioactive wastes has a large volume reduction and good durability for the final products. A feasibility study for the vitrification of concentrated boric acid wastes has been performed with developing the pre-treatment methods of powdered wastes, glass compositions using glass formulation and demonstration test. The pre-treatment method is pelletizing the powder type for stable feeding within cold crucible melter. The glass compositions should be developed considering molten glass are related with wastes reduction. High contents of sodium and boron within borate wastes give influence to waste loading. A variety of factors obtained from the demonstration test are reviewed, which is wastes feeding rate, off-gas characteristics on stack and glass characteristics of final products such as durability for implementing the wastes disposal requirement. The aim of this paper is to present the feasibility of vitrification and review the solidification method for concentrated boric acid wastes and obtain the physicochemical characteristics of solidified glass.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.207-212
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• 1996

실증규모의 수지충전식 전기투석 재생조를 사용하여 농축음극액내 바나듐의 전기화학적 환원 방법에 의한 재생거동을 조사하였다. 전기투석 분리재생 종료후 남아있는 개미산용액을 전해액으로 사용한 농축음극액내 전기투석된 철 및 코발트는 음극액의 pH를 약 4.3내외로 조절하면 전해환원에 의해 전착.제거된다. 또한 농축음극액내 바나듐은 +2가로 전해환원 되어 착화물을 이루고 있는 Vanadous picolinate 형태로 존재하기 때문에 음극액은 농축된 LOMI 제염제로 재생된다. 이 전해환원에 의한 농축음극액의 재생방법은 제염폐액의 전기투석 분리재생 후 피콜리네이트 착화제만을 재사용하는 기존의 재생개념보다 더욱 효과적으로 제염폐액을 재생시켜 재활용할 순 있는 방사성폐기물의 감용효율이 큰 향상된 제염폐액 재생공정이다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.3
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• pp.221-227
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• 2010

The solidification methods for powder wastes dried at CWDS(Concentrate Waste Drying System) in PWR have been studied in a variety of ways both at home and abroad. The solidification for these wastes has been performed using stabilization agents such as cement, paraffin and polymer. The applicability studies to maximize the reduction ratio of wastes and operational effectiveness for wastes treatment have been carried out, recently. It is necessary to pretreat the powder wastes before feeding wastes to vitrification facility because the fines flying brings about clogging of feeding pipes and off-gas treatment system or workers' exposure to radiation during maintenance. This paper describes an effective method for treatment of powder wastes to improve safety and stability of vitrification facilities.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.145-146
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• 2009

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.05a
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• pp.99-100
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• 2007

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.403.2-403
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.421-426
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• 1998

원자력발전소에서 발생되는 방사성 세탁폐액의 처리연구틀 위하여 100L/h 처리용량의 오존접촉조-활성탄탑-역삼투막-이온교환수지탑의 복합공정을 제작하고 영광 4호기에 설치하여 단위공정별 성능실험을 수행하였다. 오존에 의한 세제 제거율은 약 50％로 나타났으며, 활성탄탑을 거친후에는 거의 모든 유기물이 제거되었다. 역삼투막에 의하여 방사성핵종 제거율 설험은 원수의 부피를 1/10로 줄이는 데까지 농축도를 증가시키면서 수행하였는데, 농축도에 따라 핵종제거율이 약간 감소하는 경향은 있었으나 대체적으로 99% 정도의 제거율을 나타내었다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.151-152
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• 2009