• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.113-117
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• 1996

원자력시설 및 동위원소 이용기관에서의 인체오염사고에 대비하여, 피부제염기준을 조사하였으며, 피부제염제의 개발을 위하여 실험용 쥐를 대상으로 Co-60 및 Cs-137에 대해 비눗물, EDTA 및 KAERI-CON의 제염효과를 비교하였으며, 가장 효율적인 제염방법을 제시하였다. 각 제염제의 제염실험결과 Co-60 보다 Cs-137에 대한 제염이 더 잘 이루어졌으며, 제염횟수의 증가에 따라 방사능잔류율도 급격히 낮아졌다. KAERI-CON은 Co-60의 경우 38-55%, Cs-137의 경우에는 44-50%까지 제염효율을 보임으로서 타 제염제보다 효과적임을 확인하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.3
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• pp.199-209
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• 2014

Crevice corrosion tests were conducted to examine the corrosion properties of HYBRID (HYdrazine Base Reductive metal Ion Decontamination) which was developed to decontaminate the PWR primary coolant system. To compare the corrosion properties of HYBRID with commonly existing decontamination agents, oxalic acid (OA) and citric oxalic acid (CITROX) were also examined. Type 304 Stainless Steel (304 SS) and Alloy 600 which are major components of the primary coolant system in Pressurized Water Reactor (PWR) were evaluated. Crevice corrosion tests were conducted under very aggressive conditions to confirm quickly the corrosion properties of primary coolant system structure components which have high corrosion resistance. Pitting and IGA were occurred in crevice surface under OA and CITROX conditions. But localized corrosion was not observed under HYBRID condition. Very low corrosion rate of less than $1.3{\times}10^{-3}{\mu}m/h$ was observed under HYBRID condition for both materials. On the other hand, under OA condition, Alloy 600 indicated comparatively uniform corrosion rate of $4.0{\times}10^{-2}{\mu}m/h$ but 304 SS indicated rapid accelerated corrosion in lower case than pH 2.0. In case of HYBRID condition, general corrosion and crevice corrosion were scarcely occurred. Therefore, material integrity of HYBRID in decontamination of primary coolant system in pressurized water reactor (PWR) reactor was conformed.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.921-927
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• 1995

수지충전식 전해재생조내에서 바나듐-철-Picolinate 착화물이 함유된 모의 LOMI 제염폐액의 재생거동에 대한 공정변수의 영향을 조사하였다. 전기투석에 의해 양이온종이 제염 폐액으로부터 제거되는 재생 분리효율에 대한 전류밀도, 제염폐액 공급유량 및 재생조내 수지층두께 등 공정변수의 영향은 바나듐이온이 가장 크게 받는다. 공정변수의 영향을 총괄 파라미터인 공정변수비 $\alpha$로 정의하여 나타낼 때 재생 분리효율 95%이상을 얻기 위해서는 $\alpha$가 0.2 이하로 유지되어야 한다. LOMI 제염폐액의 재생시 전기투석 flux는 공정변수비, $\alpha$값이 증가함에 따라 철이온이 바나듐이온에 비해 더욱 커지는 경향을 보였다. 재생종료 후 발생되는 음극폐액내 철 및 코발트 등 방사성이온종은 음극액의 초기 수소이온 농도를 조절하면 침전제의 첨가 얼이 음극반응에 의해 음극액의 pH를 산성에서 알카리성으로 바꿀 수 있어, 수산화물 형태의 침전물 입자로 만들어 쉽게 제거할 수 있다. 재생시 바나듐이온은 대부분 $V^{III}$(Pic)$_2$$^{+}$ 착화물형태로 전기투석된다. 음극액으로 formate용액을 사용하면 철 및 코발트 등 방사성이온종을 제거한 음극액은 농축된 LOMI제염제로 회수하여 필요시 산화가를 조정한 후 재생된 착화제와 혼합하여 제염제로 재사용할 수 있어, 더욱 효과적으로 제염폐액을 재생하는 향상된 재생방법이다.다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.1
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• pp.35-43
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• 2015

A large amount of radioactively-contaminated gravel can be produced on the demolition/restoration of facilities related the back end of fuel cycle. However, because of the lacking in basic knowledge for decontamination of radioactive-contami-nated gravel, this study has performed the basic tests using for soil-washing. To find effective decontamination condition, several experiments were carried out for the selection of optimal decontamination agents. Washing by 0.1 M nitric acid was proved to be more effective than that by distilled water or surfactant for decontamination of uranium-contaminated gravel. In addition, crushing/grinding of uranium-contaminated gravel prior to washing was contributed to increase in of removal efficiency of uranium and reduction of decontamination time. The smaller the sizes of crushed gravel was, the more the removal efficiency increased. Also, small the sized particles improved chances for meeting the clearance requirement of the treated gravel.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.2
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• pp.91-97
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• 2010

As nuclear power plants are getting older, interests on a decontaminating process are increasingly attracting more attention. Chemical decontamination is crucial to lower the production of radioactive waste and radiation dose rate. Prior to this, oxidizers and detergents for target material should be chosen so as to decontaminate major systems and components of a nuclear power plant chemically. In order to decontaminate it properly, it is crucial to have information about the chemical composition and crystalline structure of CRUD, analyzing its samples from the target or the decontamination system with components. However, there is no program which enables the extraction of samples directly from the object or the decontamination system with components carrying genuine radioactivity. Therefore, it is limited to samples from corrosion products carrying partial radioactivity as a resource. The composition of CRUD varies considerably depending on refueling cycle because it is closely related to the constituent of basic material. After settling a target, it is crucial to analyze and obtain analytical information about CRUD as a decontamination target. In this paper, various technologies for manufacturing simulated CRUD are introduced as alternatives to unattained samples. A metal oxide or metal hydroxide was used to synthesize simulated cruds having chemical compositions and crystalline stricture similar to the actual one by 12 different methods. CRUD 4(metal oxides in the autoclave vessel) and CRUD 10(metal oxides in a crucible after hydrazing pretreatment)were chosen as the best method for Type 1 and Type 2.respectively. As these CRUD can be synthesized easily without using any specialized equipment or reagents in a short time and in large quantities, they are expected to stimulate the development of decontaminating agents and processes.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.929-936
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• 1995

LOMI 제염제의 전기화학적 제조공정 중 전하운반체의 역할 및 V$^{3+}$ 이온의 침전현상을 방지하기 위하여 첨가되는 과량의 formic acid 는 제염제 제조시에는 중요한 역할을 하지만 제염 폐기물의 양을 증가시키는 요인이 되기도 한다. EPRI 공정에서는 formate : V 의 비율(FVR)이 10:1 인 조건에서 V$^{2+}$-formate 를 제조한 후 음이온 교환 수지를 이용하여 과량의 formate 를 제거하는 공정을 사용한다. 이러한 방법으로 줄일 수 있는 FVR의 한계가 약 2.5 : 1 이다. 본 연구에서는 제염제 중 formate 의 양을 더욱 줄일 수 있는 방법으로써 V$^{2+}$-formate 제조시 용액 중에 picolinic acid를 미리 첨가하는 영향을 조사하였다. V$^{2+}$ 이온의 농도가 0.1 M 일 때 FVR 를 1.5:1 까지도 줄일 수 있음을 확인하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.1
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• pp.15-28
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• 2019

In accordance with the decommissioning plan for the Kori Unit 1 NPP, the reactor coolant system will be chemically decontaminated as soon as possible after permanent shutdown. This study developed the chemical decontamination process though the development project of decontamination technology of reactor coolant system and dismantled equipment for NPP decommissioning, which has been carried out since 2014. In this study, Oxidation/reduction process was conducted using system decontamination process development equipment of lab scale and was divided into unit and continuous processes. The optimal process time was derived from the unit process, and decontamination agent and the number of process were derived through the continuous processes. Through the unit process, the oxidation process took 5 hours and the reduction process took 4 hours. As optimum decontamination agent, the oxidizing agent was $200mg{\cdot}L^{-1}$ Permanganic acid + $200mg{\cdot}L^{-1}$ Nitric acid and the reducing agent was $2000mg{\cdot}L^{-1}$ Oxalic acid. In the case of the number of processes, all oxide films were removed during the two-cycle chemical decontamination process of STS304 and SA508. In the case of Alloy600, all oxide films were removed when chemical decontamination was performed for three cycles or more.

• Nuclear industry
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• v.20 no.5 s.207
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• pp.59-63
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• 2000

• 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.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.05a
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• pp.321.1-321
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• 2002