• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.418-418
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• 2004

풀, 토양 또는 지하수와 같은 환경시료 중에 포함된 미량 우라늄을 분석하기 위하여 핵분열 트랙 기입법을 이용하였다. 시료 전처리 방법으로 지하수 시료는 질산 산성으로 만든 후, 토양시료는 질산과 불산을 이용하여 용액화 하였으며, 풀 시료는 전기로를 이용하여 회화한 후, 질산과 불산을 이용하여 용액화 하였다. 이 환경시료 전처리용액들을 각각 0.1mL를 0.9mL Collodion 분산용액에 섞은 후, 우라늄 표준용액과 함께 플라스틱 판($6{\times}6\textrm{cm}^2$) 위에 10$\mu\textrm{\ell}$씩 점적, 건고 시키고 핵분열 트랙기입법을 이용하여 우라늄 농도를 분석하였다. 핵분열 트랙기입법을 위한 중성자조사는 한국원자력연구소 하나로 연구용원자로(열중성자 선속: $2.7{\times}10^{13}n/\textrm{cm}^2{\cdot}sec^{-1}$)에서 10분간 하였으며, 6.25M NaOH 용액($60^{\circ}C$)을 이용하여 10분간 화학 에칭 하였다. 고체트랙검출기 표면에 생성된 핵분열 트랙들은 광학현미경과 image analyzer system을 이용하여 관찰하고 계수하였다. 시료와 같이 점적한 우라늄 표준용액을 이용하여 우라늄 농도에 대한 단위면적당 트랙 수의 상관관계를 구하였으며, 이를 이용하여 시료 내 우라늄 농도를 결정하였다. 본 실험의 결과에 대한 검증을 위하여 동일 시료용액을 분리관을 이용한 전처리 과정을 거친 후 ICP-MS를 이용하여 분석하였다. 우라늄의 선택적 분리를 위하여 U-TEVA 추출크로마토그래피 분리관을 이용하였다. 본 연구의 핵분열 트랙기입법을 이용하여 환경시료를 분석하는 방법은 일반적인 분광법을 이용할 경우, 문제가 되는 방해 원소의 분리를 위한 전처리 과정이 불필요한 장점을 가지고 있으며, 1ng 정도의 미량 우라늄을 분석할 수 있었고, ICP-MS 결과와 20% 오차 이내에서 일치하였다.

• Nuclear Engineering and Technology
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• v.13 no.4
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• pp.237-244
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• 1981

The preliminary concentration of trace elements in uranium dioxide using an anion exchange resin is presented for neutron activation analysis. The uranyl solution in sulfuric acid is adjusted to the acidity of about pH 2.7 and loaded on a column of the anion exchange resin. An appropriate volume of eluates obtained from the column shows good recoveries of trace elements. By combining this preconcentration with a radiochemical separation scheme, which was developed for the determinations of impurities in aluminum, it is possible to determine 21 trace elements in reactor grade uranium dioxide.

• Analytical Science and Technology
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• v.21 no.5
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• pp.397-402
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• 2008

Uranium dioxide was dissolved with nitric acid and a trace amount of HF. The analytical conditions of a spectrophotometer were investigated to determine a trace amount of silicon in the uranium matrices without a separation process. The effects of a trace amount of HF on the determination of silicon were examined. Boric acid was used to eliminate HF the interference in the colorimetric process. The recovery of silicon in the presence of a trace amount of HF in uranium solutions with or without saturated boric acid was $103.3{\pm}0.8$ and $76.6{\pm}6.8%$, respectively. The amount of saturated boric acid did not affect the recovery of the silicon. Therefore it was possible for this procedure to measure a trace amount of silicon in a uranium matrix without a separation by a UV-VIS spectrophotometry.

• Nuclear Engineering and Technology
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• v.19 no.4
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• pp.242-248
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• 1987

A sensitive, direct method for the determination of trace amounts of uranium in solution has been developed utilizing laser-induced fluorescence spectroscopy and a fluorescence enhancing reagent 'Fluran.' Standard addition technique is incorporated into the analysis to eliminate sample matrix effects. Analytical data show that a detection limit of 0.1 ppb (part per billion) uranium has been achieved and the precision of the analysis is in the range of 5% relative standard deviation. Results using the laser fluorescence method on many sets of unknown samples have been compared against corresponding values determined by other methods.

• Analytical Science and Technology
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• v.9 no.1
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• pp.20-25
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• 1996

Trace levels of uranium and thorium in geologic samples are determined rapidly by a direct wavelength-dispersive X-ray fluorescence method. Relative intensity of scattered tube radiation was used as an internal standard to compensate for variations in instrumental operating characteristics. U and Th can be determined within a precision of ${\pm}10%$ and accuracy of ${\pm}15%$ or less with measuring times of 50 seconds for Th and 400 seconds for U, respectively. The results of XRF analysis were in good agreement with those of other methods such as nutron activation analysis and inductively coupled plasma atomic emission spectrometry.

• Journal of the Korean Chemical Society
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• v.37 no.9
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• pp.813-819
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• 1993

An ICP-AES system directly connected with a separation column was used in order to determine the trace elements in $UO_2$ powder promptly and reduce the volume of the waste solution. The outlet of a separation column, which was filled with Teflon powder ($330\;{\mu}m$) coated with tri-n-butyl phosphate (TBP) as extractant, was directly connected with sample injection tube of ICP-AES. Eleven elements including molybdenum in $UO_2$ powder were separated and determined simultaneously. Recoveries of these elements were $91{\sim}110%$ and these results were agreed with those of solvent extraction methods. This method was applicable to quality control in manufacturing nuclear fuel.

• Analytical Science and Technology
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• v.18 no.4
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• pp.263-270
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• 2005

Nuclear track is an useful tool for elemental analysis of radionuclides, such as uranium, plutonium and thorium, etc., and for elements undergoing nuclear reactions with thermal neutrons such as lithium and boron. This method has various application fields such as detecting fissionable radionuelides, measuring the fission rate in nuclear technology, analyzing cosmic radiation from meteorite, calculating the age of minerals as well as their history, etc. Track registration method has been applied to the microscopic analysis of boron and fissionable element such as uranium in KAERI. This report reviews the theoretical background of the nuclear track formation, practical procedures to obtain etched tracks and a perspective of the future.

• Nuclear Engineering and Technology
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• v.15 no.2
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• pp.142-148
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• 1983

Distribution coefficients between cation exchange resin (Dowex 50W$\times$8) and $\alpha$-hydroxyisobutric acid ($\alpha$-HIBA) are measured in order to separate traces of Sm, Eu, Gd and Dy from nuclear material. Individual separations are performed by pH gradient technique with 0.40M $\alpha$-HIBA from 3.40 to 3.60 in cation exchange resin after a group separation. Each of separated elements is determined with a fluorometric method except Gd by colorimetry. The results are applied to analyze Sm, Eu, Gd and Dy in magnesium diuranate (yellow cake).

• Journal of the Korean Ceramic Society
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• v.39 no.2
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• pp.204-209
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• 2002

In this study, $UO_4{\cdot}2NH_4F$, the precipitates which has low solubility, was obtained by chemical precipitation method to recover and reuse the trace uranium from the liquid waste producing in AUC process and for this compound it was characterized by means of chemical analysis, TG-DTA, XRD and FT-IR analyses. This compound was analyzed as $UO_4{\cdot}2NH_4F$ and shape of this precipitate was hexagonal type, having the size of 2∼3 ${\mu}m$. Also, the intermediates were obtained as $UO_4F,\;UO_4,\;UO_3,\;and\;U_3O_8$ by the thermal decomposition over the temperature of 220, 310, 515 and 640$^{\circ}C$, respectively. It is concluded that under the condition of a constant heating rate of 5$^{\circ}C$/min in air atmosphere range of between room temperature and 800$^{\circ}C$, thermal decomposition reaction mechanism of $UO_4{\cdot}2NH_4F$ is as follow; $UO_4{\cdot}2NH_4F{\rightarrow}UO_4F{\rightarrow}UO_4{\rightarrow}UO_3{\rightarrow}U_3O_8$.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.192-197
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• 1998

사용후핵연료는 열전도도가 극히 불량하다. 그러므로 지금까지는 파단면을 관찰하거나 또는 성분분석을 위해 EPMA을 이용할 때는 시편 표면을 Au나 란소 등으로 증착시키고 있다 그러나 사용후 핵연료에서는 강력한 방사선이 방출되므로 시편의 증착처리는 핫셀(hot cell)에서 원격조정기(manipulator)를 사용하여 수행하므로 많은 어려움이 있다. 특히 시편 표면의 Au나 탄소의 증착시에는 균일한 증착이 필요한데, 핫셀내에 설치한 기기는 유지 보수의 어려움으로 양호한 진공도 유지가 어려워 시편 표면의 균질한 증착은 문제점으로 되어 있다. 이에 본 연구에서는 이산화우라늄 소결체를 표면의 증착처리 없이도 파단면 관찰이나 성분 분석을 할 수 있는 방법을 연구하여 silber paint법을 개발하였다. 특히 탄소가 미량 함유된 시편을 탄소 증착처리를 하면 증착된 탄소와 시편에 함유된 탄소를 분리해야 하는 어려운 점이 있으므로 이러한 경우에는 silber paint 법이 아주 편리하다.