• 제목/요약/키워드: Self-decontamination

검색결과 18건 처리시간 0.021초

흙의 자체정화능력을 이용한 오염된 토양정화 (Application of Soil's Self-Decontamination Ability to Contaminated Ground)

  • 정진섭;정정권;김태형
    • 한국물환경학회지
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    • 제22권4호
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    • pp.632-638
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    • 2006
  • 최근에 오염된 토양을 정화하기 위해서 다양한 방법들이 사용되고 있으나 이들 대부분은 이미 오염된 토양에 대한 정화기술로서 많은 비용이 수반되는 단점이 있다. 본 연구에서는 이들 방법과는 달리 잠재적인 토양오염지역에서 오염되기 전이나 혹은 진행 중일 때 지형학적인 특징, 지표 위나 아래의 배수시스템의 재배열 및 선행계획을 통해 토양자체의 정화능력을 이용하는 새로운 정화방법을 고찰하였다. 즉, 토양자체 정화과정이 왜, 어떻게 발전되는가에 대해 단계적으로 규명하였다. 해안지역에서 오염된 바닷물의 침투와 거주지역에서 유해 라돈가스($^{222}Rn$)의 조절 및 제거 등 두 가지 사례를 통해 흙의 자체정화 능력을 이용한 토양정화방법의 효율성을 평가하였다.

201Tl의 생산과정에서 발생한 방사성 폐기물의 제염 효율 평가 (Evaluation of the Decontamination Efficiency of Radioactive Wastes Generated during the Production of 201Tl)

  • 허재승;김상록;김기섭;안윤진;김정민
    • 대한방사선기술학회지:방사선기술과학
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    • 제44권5호
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    • pp.481-487
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    • 2021
  • This study was conducted for the purpose of efficient radioactive waste disposal and management. Experiment was evaluated the decontamination efficiencies of the four types decontamination materials(Water, Alcohol, Decontamination Water, Decontamination Gel) with radioactive wastes generated during radio-pharmaceutical production process at Korea Institute Radiological and Medical Sciences(KIRAMS). The radioactive waste sample used in experiment is a lead plate of the fume hood that was disposed in April, 2019. In the experimental method, radioactive waste was measured before and after decontamination using a HPGe semiconductor detector and Gamma survey meter. The measured values before and after decontamination were evaluated for decontamination efficiency as a percentage. As a result, it was confirmed that a lot of specific activity and surface dose rate was removed from the radioactive wastes. In particular, when decontamination water was used, most of the radioactivity of radioactive wastes was removed. Considering these results, if decontamination water is used in decontamination of radioactive waste, decontamination efficiency equivalent to the disposition criteria can be expected with just one decontamination treatment. In addition, in the case of water and alcohol, only on decontamination was effective in approximately 75% and 95%. Otherwise, when decontamination gel was used, it was confirmed that the largest deviation occurred among all experimental results.

한 단계 자가부식 접착제를 이용한 복합레진 수복 시 타액오염 후 처치 방법에 따른 미세인장강도 비교 (Effect of Saliva Decontamination on Bond Strength of 1-step Self-etching Adhesives to Dentin of Primary Posterior Teeth)

  • 이준희;김신;정태성;신종현;이은경;김지연
    • 대한소아치과학회지
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    • 제46권3호
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    • pp.274-282
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    • 2019
  • 이 연구의 목적은 유치에서 한 단계 자가부식 접착제를 이용한 레진수복 시 타액오염 후 처치과정에 따른 미세인장강도를 비교하는 것이다. 건전한 유구치를 접착제 사용에 따라 각각 $Scotchbond^{TM}$ Universal Adhesive (SBU), All-Bond $Universal^{(R)}$ (ABU), and $Tetric^{(R)}$ N Bond Universal (TBU)의 3 그룹으로 나누어 무작위로 분배하였다. 각 그룹은 접착제 도포 후 처치과정에 따라 7가지 하위분류로 나누었다. Subgroup I은 대조군으로써, 타액오염 없이 제조사 권고사항에 따라 접착제를 적용하였다. Subgroup II - IV는 접착제 광중합 전에 타액오염을 시행하였고, subgroup V - VII는 접착제 광중합 후에 타액오염을 시행하였다. 그 후 subgroup II, V는 건조, subgroup III, IV는 수세 후 건조, subgroup IV, VII는 수세 후 건조, 그리고 접착제 재도포를 시행하였다. SBU와 ABU에서 subgroup I, IV, VII의 미세인장강도가 subgroup II, III, V, VI의 미세인장강도보다 유의하게 높았다. TBU에서 subgroup I, IV의 미세인장강도가 subgroup II, III, V, VI의 미세인장강도보다 유의하게 높았다. 이 연구 결과, 임상가는 한 단계 자가부식 접착제를 이용한 레진 수복 시 타액과 수분의 오염으로부터 철저하게 격리를 지켜야 하지만 그럼에도 불구하고 타액오염이 발생하였다면, 수세 및 건조 후 접착제를 재도포할 것을 권장한다.

The effect of saliva decontamination procedures on dentin bond strength after universal adhesive curing

  • Kim, Jayang;Hong, Sungok;Choi, Yoorina;Park, Sujung
    • Restorative Dentistry and Endodontics
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    • 제40권4호
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    • pp.299-305
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    • 2015
  • Objectives: The purpose of this study was to investigate the effectiveness of multiple decontamination procedures for salivary contamination after curing of a universal adhesive on dentin bond strength according to its etch modes. Materials and Methods: Forty-two extracted bovine incisors were trimmed by exposing the labial dentin surfaces and embedded in cylindrical molds. A universal adhesive (All-Bond Universal, Bisco) was used. The teeth were randomly divided into groups according to etch mode and decontamination procedure. The adhesive was applied according to the manufacturer's instructions for a given etch mode. With the exception of the control groups, the cured adhesive was contaminated with saliva for 20 sec. In the self-etch group, the teeth were divided into three groups: control, decontamination with rinsing and drying, and decontamination with rinsing, drying, and adhesive. In the etch-and-rinse group, the teeth were divided into four groups: control, decontamination with rinsing and drying, decontamination with rinsing, drying, and adhesive, and decontamination with rinsing, drying, re-etching, and reapplication of adhesive. A composite resin (Filtek Z350XT, 3M ESPE) was used for filling and was cured on the treated surfaces. Shear bond strength was measured, and failure modes were evaluated. The data were subjected to one-way analysis of variation and Tukey's HSD test. Results: The etch-and-rinse subgroup that was decontaminated by rinse, drying, re-etching, and reapplication of adhesive showed a significantly higher bond strength. Conclusions: When salivary contamination occurs after curing of the universal adhesive, additional etching improves the bond strength to dentin.

Electrochemical Decontamination of Metallic Wastes Contaminated with Uranium Compounds in a Neutral Salt Electrolyte

  • Park, W. K.;Y. M. Yang;C. H. Jung;H. J. Won;W. Z. Oh;Park, J. H.
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.689-695
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    • 2003
  • Electrochemical decontamination process has been applied for recycle or self disposal with authorization of large amount of metallic wastes contaminated with uranium compounds such as $UO_2$, ammonium uranyl carbonate (AUC), ammonium di-uranate (ADU), and uranyl nitrate(UN) with tributylphosphate(TBP) and dodecane, which are generated by dismantling the contaminated system components and equipment of a retired uranium conversion plant in Korea Atomic Energy Research Institute (KAERI). Electrochemical decontamination for metallic wastes contaminated with uranium compounds was evaluated through the experiments on the electrolytic dissolution of stainless steel as the material of the system components in neutral salt electrolytes. The effects of type of neutral salt as the electrolyte, current density, and concentration of electrolyte on the dissolution of the materials were evaluated. Decontamination performance tests using the specimens taken from a uranium conversion plant were quite successful with the application electrochemical decontamination conditions obtained through the basic studies on the electrolytic dissolution of structural material of the system components.

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과산화수소 증기를 이용한 유사화학작용제의 제독 (Decontamination of Chemical Warfare Agent Simulants using Vapor-phase Hydrogen Peroxide)

  • 김윤기;유현상;김민철;황현철;류삼곤;이해완
    • Korean Chemical Engineering Research
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    • 제52권3호
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    • pp.360-365
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    • 2014
  • 과산화수소 증기는 기존 염소계열의 멸균제에 비해 부식성이 낮아 제약 및 의료 분야의 실내멸균제로 사용되며, 암모니아 가스 추가 시 화학작용제의 제독성능이 있다고 알려져 있다. 본 연구에서는 과산화수소 증기를 이용하여 HD, GD, VX의 유사작용제인 CEPS, DFP, dimethoate 등에 대한 제독효율을 확인하였다. 이를 위해 자체 구성한 과산화수소 기화장치에서 발생시킨 증기를 제독챔버에 주입하여 반응시간을 유지하였다. 제독 후 잔류물을 GC/MS로 분석한 후 제독효율을 계산하였고, 각각의 유사작용제에 대한 반응 생성물을 통해서 화학작용제의 반응 메카니즘과 유사함을 확인하였다. 실험결과 CEPS는 30%의 상대습도에서 60분의 반응시간에 완전제독 되었고, 암모니아 가스 주입의 동반하에서 DFP는 30분, dimethoate는 150분의 반응시간에 완전제독되었다.

한빛원전 폐수지 제염공정 개발연구 (Research and Development for Decontamination System of Spent Resin in Hanbit Nuclear Power Plant)

  • 성기홍
    • 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.

TRIGA 연구로 해체 시 발생하는 덕트 폐기물의 제염 (Decontamination of Duct Waste Arising from the Decommissioning of TRIGA Research Reactor)

  • 최왕규;이근우;정경환;오원진;박진호
    • 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.

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Development of Micro-Blast Type Scabbling Technology for Contaminated Concrete Structure in Nuclear Power Plant Decommissioning

  • Lee, Kyungho;Chung, Sewon;Park, Kihyun;Park, SeongHee
    • 방사성폐기물학회지
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    • 제20권1호
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    • pp.99-110
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    • 2022
  • In decommissioning a nuclear power plant, numerous concrete structures need to be demolished and decontaminated. Although concrete decontamination technologies have been developed globally, concrete cutting remains problematic due to the secondary waste production and dispersion risk from concrete scabbling. To minimize workers' radiation exposure and secondary waste in dismantling and decontaminating concrete structures, the following conceptual designs were developed. A micro-blast type scabbling technology using explosive materials and a multi-dimensional contamination measurement and artificial intelligence (AI) mapping technology capable of identifying the contamination status of concrete surfaces. Trials revealed that this technology has several merits, including nuclide identification of more than 5 nuclides, radioactivity measurement capability of 0.1-107 Bq·g-1, 1.5 kg robot weight for easy handling, 10 cm robot self-running capability, 100% detonator performance, decontamination factor (DF) of 100 and 8,000 cm2·hr-1 decontamination speed, better than that of TWI (7,500 cm2·hr-1). Hence, the micro-blast type scabbling technology is a suitable method for concrete decontamination. As the Korean explosives industry is well developed and robot and mapping systems are supported by government research and development, this scabbling technology can efficiently aid the Korean decommissioning industry.

중성염 용액 내에서 우라늄으로 오염된 금속성 해체폐기물의 전해제염 (Electrolytic Decontamination of the Dismantled Metallic Wastes Contaminated with Uanium Compounds in Neutral Salt Solutions)

  • 최왕규;이성렬;김계남;원휘준;정종헌;오원진
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 학술논문집
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    • pp.72-80
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    • 2004
  • 국내의 가동 중지된 우라늄 변환시설의 해체 시 다량의 우라늄으로 오염되어 있는 금속성 폐기물의 재활용 또는 자체처분을 위한 제염기술로 중성염 전해액을 사용하는 전해제염 공정의 적용성을 평가하기 위하여 우라늄 변환시설 내부설비의 주 구성 재료인 SUS-304 및 Inconel-600에 대한 전기화학적 용해거동 연구를 수행하였다. 이를 위하여 중성염 전해질의 형태, 전해질의 농도, 전류밀도, 처리시간과 같은 전해제염 조건들이 금속 재료의 용해에 미치는 영향을 평가하였다. 모의 시편을 사용한 비방사성 전해용해 실험 결과를 근거로 실제 우라늄 변환시설로부터 인출한 $UO_2$, AUC (ammonium uranyl carbonate) 및 ADU (ammonium diuranate) 오염시편에 대해 $Na_2SO_4$$NaNO_3$ 중성염 용액에서 전해 제염실험을 수행하였으며, 오염물의 종류 및 오염 준위의 대소와는 관계없이 모든 시편에 대하여 10분 이내의 짧은 시간 내에 자체처분 기준치 이하로 $\beta$ 방사능 준위를 감소시킴으로써 본 중성염 전해제염이 매우 성공적임을 확인하였다.

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