• 방사선산업학회지
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• 제9권4호
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• pp.217-221
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• 2015

When reactor coolant leaks occur due to cracks of a steam generator's tube, radioactive materials contained in the primary cooling water in nuclear power plant are forced out toward the secondary systems. At this time the secondary water purification resin in the ion exchange resin tower of the steam generator blowdown system is contaminated by the radioactivity of the leaked radioactive materials, so we pack this in special containers and store temporarily because we could not dispose it by ourselves. If steam generator tube leakage occurs, it produces contaminated spent resins annually about 5,000~7,000 liters. This may increase the amount of nuclear waste productions, a disposal working cost and a unit price of generating electricity in the plant. For this reasons, it is required to develop a decontamination process technique for reducing the radioactive level of these resins enough to handle by the self-disposal method. In this research, First, Investigated the structure and properties of the ion exchange resin used in a steam generator blowdown system. Second, Checked for a occurrence status of contaminated spent resin and a disposal technology. Third, identified the chemical characteristics of the waste radionuclides of the spent resin, and examined ionic bonding and separation mechanism of radioactive nuclear species and a spent resin. Finally, we carried out the decontamination experiment using chemicals, ultrasound, microbubbles, supercritical carbon dioxide to process these spent resin. In the case of the spent resin decontamination method using chemicals, the higher the concentration of the drug decontamination efficiency was higher. In the ultrasound method, foreign matter of the spent resin was removed and was found that the level of radioactivity is below of the MDA. In the microbubbles method, we found that the concentration of the radioactivity decreased after the experiment, so it can be used to the decontamination process of the spent resin. In supercritical carbon dioxide method, we found that it also had a high decontamination efficiency. According to the results of these experiments, almost all decontamination method had a high efficiency, but considering the amounts of the secondary waste productions and work environment of the nuclear power plant, we judged the ultrasound and supercritical carbon dioxide method are suitable for application to the plant and we established the plant applicable decontamination process system on the basis of these two methods.

• 한국염색가공학회지
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• 제32권2호
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• pp.73-79
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• 2020

Pursuing the fabric materials for military chemical warfare protective clothing with the improved detoxification properties, this study investigated the simple and effective cotton treatment method using pad-dry-cure process and 3-aminopropyltrimethox ysilane(APTMS) solution for surface amination. Detoxification properties of the untreated and treated cotton fabrics were evaluated via decontamination of chemical warfare agent simulant, DFP(diisopropylfluorophosphate). The surface aminated cotton fabric increased the rate of the hydrolysis of DFP by the factor of 3 and the decontamination ratio reached 88.2% after 24h. Therefore, the surface amination of the cotton fabric with APTMS can be an effective pathway to prepare the material for protective clothing against chemical warfare agents.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.720-724
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• 2003

국내의 가동중지 된 TRIGA 연구로의 해체 시 발생하는 다양한 덕트 폐기물의 자체처분을 위한 제염 공정을 개발할 목적으로 TRIGA 연구로에서 직접 인출한 덕트 시편을 대상으로 오염물의 성상을 조사하였고, 이를 통해 적절한 제염공정을 선정하였다 페인트 도막이 입혀진 덕트 내부계통 표면은 주로 Co-60과 Cs-137로 오염이 되어 있었으며, 이들 핵종은 페인트 층 내부뿐만 아니라 덕트 재료인 함석 표면의 아연 도금막까지 침투되어 있음을 알 수 있었다. 이들 표면 오염을 제거하기 위한 공정으로 NaOH와 황산을 교대로 사용하는 두 단계의 화학제염을 제시하였으며, 이들 제염제를 사용하는 제염공정의 적용을 통해 덕트 폐기물을 효과적으로 제염할 수 있었다.

• 공업화학
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• 제4권1호
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• pp.171-177
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• 1993

원자로 냉각계통의 방사성 오염물질을 제거하기 위한 제염공정에서 유기산에 용해된 금속이온들은 이온교환 수지를 통과하면서 제거된다. 그러나 제염용액내 유기산들은 용액내 금속이온과 착화합물을 형성하여 이온교환수지에 대한 친화도를 감소시킨다. 이같은 관점에서 착화합물 형성이 이온교환공정에 미치는 영향 해석을 위해 코발트와 철 이온을 대상으로 Amberlite IRN-77 양이온수지와의 이온교환실험을 수행하였다. 실험결과에서 화학제염제로 사용된 유기산 가운데 EDTA는 철 이온보다 코발트 이온과 강한 착화합물을 형성하여 코발트 이온의 수지에 대한 이온교환용량을 현저히 감소시켜 주는 성분으로 나타났다. 반면에, Oxalic Acide와 Citric Acide의 영향은 미미하였다. 또한, 실험결과로부터 이들 금속이온 들에 대한 단일 성분계 및 2성분계 비선형 평형식을 결정하였다.

• 방사성폐기물학회지
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• 제8권2호
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• pp.91-97
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• 2010

국내 원자력발전소의 가동년수 경과에 따른 방사능 오염증가로 제염공정에 대한 관심은 점차 점증되어 가고 있다. 화학제염은 방사성폐기물의 생성과 방사선량율을 낮추는데 매우 중요하다. 이에 앞서, 원전 주요 계통 및 부품 등의 화학제염을 위해서는 대상 재질에 적합한 산화제 및 제염제를 우선 선정하여야 한다. 이를 위해서는 제염대상물 혹은 제염대상 계통에서 채취한 크러드에 대한 각종 분석을 실시하여 크러드의 화학조성 및 결정구조에 대한 정보를 확보해야 하나 실제적으로 방사능을 띤 계통으로부터 시료를 직접 채취할 수 있는 특별한 프로그램이 마련되어 있지 않는 한 극히 제한된 방사능을 띠고 있는 부식산화물의 자료만을 얻을 수 있다. 크러드의 조성은 모재의 성분과도 밀접한 관계가 있기 때문에 재장전 주기에 따라서도 차이가 많다. 따라서 가능한 한 제염대상을 선정한 다음 제염대상으로 채취한 크러드에 대한 각종 분석자료를 확보하거나 분석을 실시하여야 한다. 본 논문은 미확보 시료에 대한 대안으로 모의크러드를 다양한 방법으로 제조하는 기술에 대해 언급하였다. 금속 산화물과 금속 수화물이 12가지의 각기 다른 방법으로 실제 시료와 유사한 화학조성과 결정구조를 지닌 모의크러드의 합성에 사용되어졌다. CRUD#4(압력용기속의 금속산화물)와 CRUD#10(하이드라진 전 처리후 도가니속의 금속산화물)시료가 Type 1, 2에 대해 가장 양호하게 합성되어졌다. 이들 크러드 시료들은 특별한 장비를 사용하지 않고도 짧은 시간 내에 반응이 이루어지고 많은 량의 시료를 쉽게 합성할 수 있게 됨으로서 제염제와 제염공정을 개발하는데 매우 유용하게 활용될 수 있을 것으로 기대된다.

• 자원리싸이클링
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• 제8권3호
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• pp.18-25
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• 1999

화학제염이나 전지화학제염을 통해 발생된 방사성 폐액을 정화처리할 수 있는 새로운 방법으로, 다공성 활성탄소섬유(ACF)상에서 폐액중 코발트이온의 전기적 흡·탈착에 대한 연구를 수행하였다. 회전원판 전극을 사용하여 순환전압전류법으로 전기이중층 충전만이 발생하는 전위 영역을 조사하였다. ACF 전극을 사용한 회분식 전기흡착 실험결과, 음의 전위 가용은 저위 미가용 시의 흡착에 비해 코발트이온의 흡착을 증가시켰다. 또한 흡착된 코발트 이온은 역전된 가용전위에 의해 용액으로 용출되었으며 이와 동시에 탄소체 전극이 재생되어, 전기흡착 공정의 가역성을 확인 할 수 있었다.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1519-1523
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• 2021

Radioactive iodine (¹³¹I) released from nuclear power plants has been a critical environmental concern for workers. The effective trapping of radioactive iodine isotopes from the off-gas stream generated from nuclear facilities is an important issue in radioactive waste treatment systems evaluation. Numerous studies on retaining methyl iodide (CH₃I¹³¹) by impregnated activated carbons under the high content of moisture have been extensively studied so far. But there have been no good results on how to remove methyl iodide at high humid conditions up to now. A new challenge is to introduce other promising impregnating chemical agents that are able to uptake enough radioactive methyl iodide under high humid conditions. In order to develop a good removal efficiency to control radioiodine gas generated from a high humid process, activated carbons (ACs) impregnated with triethylene diamine (TEDA) and qinuclidine (QUID) were prepared. In addition, the removal efficiencies of the activated carbons (ACs) under humid conditions up to 95% RH were evaluated by applying the standard method specified in ASTM-D3808. Quinuclidine impregnated activated carbon showed a much higher decontamination factor above 1,000, which is enough to meet the regulation index for the iodine filters in nuclear power plants (NPPs).

• 펄프종이기술
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• 제30권4호
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• pp.18-27
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• 1998

Biopulping is defined as the treatment of wood chips with lignin-degrading fungi prior to pulping. Fungal pretreatment prior to mechanical pulping reduces electrical energy requirements during refining or increases mill throughput, improves paper strength, reduces the pitch content, and reduces the environmental impact of pulping. Our recent work involved scaling up the biopulping process towards the industrial level, investigating both the engineering and economic feasibility. We envision the process to be done in either a chip-pile or silo-based system for which several factors need to be considered: the degree of decontamination, a hospitable environment for the fungus, and the overall process economics. Currently, treatment of the chips with low-pressure steam is sufficient for decontamination and a simple, forced ventilation system maintains the proper temperature, humidity, and moisture conditions, thus promoting uniform growth of the fungus. The pilot-scale trial resulted in the successful treatment of 4 tons of wood chips (dry weight basis) with results comparable to those on a laboratory. Larger, 40-ton trials were also successful, with energy savings and paper properties comparable with the laboratory scale. The overall economics of the process also look very favorable and can result in significant annual savings to the mill. Although the current research has focused on biopulping for mechanical pulping, it is also beneficial for sulfite chemical pulping and some applications to recycled fiber have been investigated.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1957-1963
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• 2019

A UVC photo-Fenton advanced oxidation process (AOP) was studied to develop a process for the decomposition of oxalic acid waste generated in the chemical decontamination of nuclear power plants. The oxalate decomposition behavior was investigated by using a UVC photo-Fenton reactor system with a recirculation tank. The effects of the three operational variables-UVC irradiation, H₂O₂ and Fenton reagent-on the oxalate decomposition behavior were experimentally studied, and the behavior of the decomposition product, CO₂, was observed. UVC irradiation of oxalate resulted in vigorous CO₂ bubbling, and the irradiation dose was thought to be a rate-determining variable. Based on the above results, the oxalate decomposition kinetics were investigated from the viewpoint of radical formation, propagation, and termination reactions. The proposed UVC irradiation density model, expressed by the first-order reaction of oxalate with the same amount of H₂O₂ consumption, satisfactorily predicted the oxalate decomposition behavior, irrespective of the circulate rate in the reactor system within the experimental range.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.336-336
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• 2004

EDTA contained in decontamination wastes can cause complexation of radioactive captions resulting from its various treatment process such as chemical precipitation, and ion exchange etc. It might also import for elevated teachability and higher mobility of cationic contaminants from conditioned wastes such as waste immobilized in cement or other matrices. Therefore, various cheated or unchlelated EDTAS must be treated to environmentally safe materials.(omitted)