• Nuclear Engineering and Technology
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• 제39권6호
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• pp.731-736
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• 2007

Radioactive organic wastes containing acetone, alcohol, and particularly tributyl phosphate (TBP)/dodecane contaminated with uranium are extracted from the PUREX process and the decontamination of related equipment. An evaporation method that utilizes existing DU oxidation apparatuses and ventilation systems and a typical muffle furnace installed with an aspirating system are adopted. A separation method using phosphoric acid especially for the TBP/dodecane waste is also studied and evaluated. The results show that a simple evaporation process is utilizable for wastes containing acetone or alcohol with a lower boiling point. A modified muffle furnace is more appropriate to dispose directly of organic wastes having a higher boiling point, such as TBP/dodecane, without generating a condensed waste solution. It is recommended that, when the uranium concentration of TBP/dodecane waste is much higher than stipulated levels, separation technology should be applied to remove uranium from the mixture. Each type of solvent after separation can then be considered disposable below the regulatory limit in the modified furnace discussed in this study.

• 대한화학회지
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• 제5권1호
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• pp.84-87
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• 1961

A polarographic method for rapid determination of Uranium in the presence of foreign ions was proposed. The method is based on the measurement of polarogram in the sulfuric acid as supporting electrolyte. In this medium Uranyl ions give well defined reduction waves, and half-wave potentials are -0.19V vs. S.C.E. as first wave, and uncertain volt. vs. S.C.E. as second wave in $2.4 N-H_2SO_4.$ The first wave has a linear relationship between the concentration of Uranyl ion and wave height. The author also studied a method for rapid determination of Uranium in Korean monazite sand without eliminating the foreign ions. The Korean monazite sands were analyzed by this method and satisfactory result were obtained.

• Journal of Radiation Protection and Research
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• 제18권2호
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• pp.61-69
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• 1993

우라늄 피폭후 효소활성도가 내부피폭의 biomarker로서의 가능성을 연구하기 위하여 수서생물인 잉어(Caprinus carpio)의 복강내 우라늄 투여시 간조직에서 일어나는 여러가지 효소계의 변화를 조사하였다. 이러한 효소활성도의 변화는 우라늄 내부피폭의 biomarker로서 가능성을 가지고 있으며 연구결과는 다음과 같다. 1) 6일째까지 우라늄을 주사하여 적출한 간에서의 전체단백질량은 계속 감소하고 있다. 2) 세포내의 lysosome내에 함유하고 있는 acid pretense와 ${\beta}-glucuronidase$의 활성도는 6일째 투여후까지 활성도가 감소하고 있다. 3) Alkaline phosphatase의 경우 6일째 우라늄 투석후까지 증가하고 있으며 반대로 acid phosphatase의 경우 6일째 우라늄 투여후까지 활성도가 급격히 증가하였고 glutamate oxaloacetate transaminase의 활성도는 완만하게 증가하고 있다. 4) Creatine kinase의 활성도는 완만한 감소를 보이고 있으며 malate dehydrogenase는 첫번 우라늄 투여후에 활성도가 급격히 감소하였고 3일째 우라늄 투여후에는 활성도가 거의 나타나지 않았다.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1476-1484
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• 2023

Laboratory experiments and point monitoring of reservoir sediments have proven that stable sulfate reduction (SSR) can lower the concentrations of toxic metals and sulfate in acidic groundwater for a long time. Here, we hypothesize that SSR occurred during in situ leaching after uranium mining, which can impact the fate of acid groundwater in an entire region. To test this, we applied a sulfur isotope fractionation method to analyze the mechanism for natural attenuation of contaminated groundwater produced by acid in situ leaching of uranium (Xinjiang, China). The results showed that δ³⁴S increased over time after the cessation of uranium mining, and natural attenuation caused considerable, area-scale immobilization of sulfur corresponding to retention levels of 5.3%-48.3% while simultaneously decreasing the concentration of uranium. Isotopic evidence for SSR in the area, together with evidence for changes of pollutant concentrations, suggest that area-scale SSR is most likely also important at other acid mining sites for uranium, where retention of acid groundwater may be strengthened through natural attenuation. To recapitulate, the sulfur isotope fractionation method constitutes a relatively accurate tool for quantification of spatiotemporal trends for groundwater during migration and transformation resulting from acid in situ leaching of uranium in northern China.

• 방사선산업학회지
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• 제17권4호
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• pp.457-469
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• 2023

The clearance level by nuclide is announced by the Nuclear Safety and Security Commission. However, the clearance level of uranium existing in nature has not been announced, and research is needed. Therefore, the purpose of this study was to evaluate the clearance level of uranium nuclides appropriate to domestic conditions preliminary. For this purpose, this study selected major processes for recycling metal wastes and analyzed the exposure scenarios and major input factors by investigating the characteristics of each process. Then, the radiation dose to the general public and workers was evaluated according to the selected scenarios. Finally, the results of the radiation dose per unit radioactivity for each scenario were analyzed to derive the clearance level of uranium in metal waste. The results of the radiation dose assessment for both the general public and workers per unit radioactivity of uranium isotopes were shown to meet the allowable dose (individual dose of 10 µSv y^-1 and collective dose of 1 Man-Sv y^-1) regulated by the Nuclear Safety and Security Commission. The most conservative scenarios for volumetric and surface contamination were evaluated for the handling of the slag generated after the melting of the metal waste and the direct reuse of the contaminated metal waste into the building without further disposal. For each of these scenarios, the radioactivity concentration by uranium isotope was calculated, and the clearance level of uranium in metal waste was calculated through the radioactivity ratio by enrichment. The results of this study can be used as a basic data for defining the clearance level of uranium-contaminated radioactive waste.

• 한국지구과학회지
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• 제31권3호
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• pp.205-213
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• 2010

옥천대 우라늄 광화대 부근 퇴적암 지하수에 대한 수리지화학적 연구를 수행하여 옥천대 우라늄 광화대와 대전지역 우라늄 지하수와의 성인적 관련성을 고찰하였다. 지하수의 pH는 6.4-8.1의 범위로 중성에서 약칼리성 특성을 보이며, Eh는 대체로 -50-225 mV의 범위로서 일부는 환원성 환경의 특성을 보인다. 지하수는 탄산염광물의 용해반응으로 $Ca^{2+}$ 및 $HCO_3^-$ 함량이 우세한 Ca-$HCO_3^$ 유형에 해당된다. 석탄광산 폐수에서는 $1165{\mu}g/L$의 우라늄이 검출되었으나 지하수내 우라늄 함량은 $3.2{\mu}g/L$ 이하로 매우 낮다. 우라늄 광화대 부근 지하수에서 낮은 우라늄 함량은 낮은 Eh를 보이는 수리지화학적 특성에 기인한다. 대전지역 지하수 내 우라늄은 옥천대 우라늄 광화대로부터 공급되지는 않은 것으로 판단된다.

• 방사성폐기물학회지
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• 제9권2호
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• pp.63-71
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• 2011

우라늄 오염토양을 동전기제염 시 많은 양의 동전기 침출액이 발생한다. 발생된 우라늄 침출액을 재이용하기 위한 처리기술이 개발되었다. 동전기제염 시 발생된 우라늄침출액 내의 우라늄농도는 180 ppm이었고, Mg(II), K(I), Fe(II), Al(III) 농도는 20 ppm~1,210 ppm이었다. 우라늄침출액의 최적 처리공정은 혼합, 응집, 침전, 농축, 그리고 여과로 구성된다. 침전액의 pH를 11로 맞추기 위해, calcium hydroxide는 3.0g/100ml 그리고 sodium hydroxide는 2.7g/100ml이 필요했다. 여러 침전실험 결과 NaOH+0.2g alum+0.15g magnetite가 여과를 위한 최적 침전혼합제로 선정되었다. NaOH+0.2g alum+0.15g magnetite 투입 시 침전입자의 평균크기는 $600\;{\mu}m$이었다. pH=9에서 침전 후 상등액에 총 금속농도가 가장 낮았기 때문에, 최적 침전을 위하여 먼저 0.2g/100ml alum와 0.15g/100ml magnetite 투입한 후 pH=9일 때까지 sodium hydroxide을 투입하여야 한다.

• 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.

• 약학회지
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• 제27권1호
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• pp.21-28
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• 1983

Distribution volume (Vd$_{ss}$ ) of a model basic drug, tetraethylammonium bromide (TEA) at a steady-state decreased sinificantly in glycerol and uranium-renal failure rats. Assuming carrier-mediated transport of TEA into tissues, the theoretical $Vd_{ss}$ of TEA decreases in an exponential way as the plasmal concentration of TEA increases. The relationship between $Vd_{ss}$ and plasma concentration of TEA in the experimental renal failure (ERF)-rats was similar. Therefore, the decrease in $Vd_{ss}$ of TEA in the ERF-rats seemed to be due to the saturation of the carrier system that are responsible for the tissue distribution of TEA, by the elevated plasma concentration of TEA in the ERF-rats. ERF was induced to rats with glycerol, folate, salicylate, uranium and gentamicin, respectively..

• 방사성폐기물학회지
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• 제18권4호
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• pp.457-464
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• 2020

In this study, extraction of uranium(VI) from an aqueous nitric acid solution was investigated using tri-n-butyl phosphate (TBP) as an extractant in an ionic liquid, 1-alkyl-3-methylimidazolium bis (trifluoromethylsulfonyl)imide ([Cnmim][Tf2N]). The distribution ratio of U(VI) in 1.1 M TBP/[Cnmim][Tf2N] was significantly high when the concentration of nitric acid was low. The value of the distribution ratio decreased as the concentration of the nitric acid increased at lower acidities, and then increased with a nitric acid concentration of up to 8 M. This can be attributed to the different extraction mechanisms of U(VI) based on nitric acid concentrations. Thus, a cation exchange at low acidity levels and an ion-pair extraction at high acidity levels were suggested as the extraction mechanism of U(VI) in the TBP/[Cnmim][Tf2N] system.