• 제목/요약/키워드: uranium isotopes

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지질시료 중의 U과 Th 분석 및 자연방사성동위원소 측정을 위한 화학적 분리 (A Sequential Separation Procedure for the Determination of Uranium, Thorium and Their Isotopes in Geological Materials)

  • 김정석;최광순
    • 분석과학
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    • 제10권5호
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    • pp.307-314
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    • 1997
  • 지질시료 중의 U과 Th을 유도결합플라즈마 원자방출분광법으로 정량하기 위해 시료를 혼산으로 분해하고 TTA(thenoyltrifluoroacetone)와 TOA (tri-n-octylamine) 추출제를 이용하여 계통적으로 용매추출한 다음 HCl 용액으로 역추출하여 분리하였다. 표준암석 NIST SRM 278에 대한 분석결과는 NIST 및 다른 비파괴분석 결과와 비교하여 양호하였다. 알파선분광법으로 U과 Th의 자연방사성 동위원소를 측정하기 위해 추출분리한 각각을 음이온교환크로마토그래피로 정제하였다.

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Analysis of the Irradiated Nuclear Fuel Using the Heavy Atom and Neodynium Isotope Correlations with Burnup

  • Kim, Jung-Suk
    • Nuclear Engineering and Technology
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    • 제29권4호
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    • pp.327-335
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    • 1997
  • The correlation of isotope composition of uranium, plutonium and neodymium with the burnup in M uranium dioxide fuel has been investigated experimentally. The total and fractional($^{235}$ U) burnup were determined by Nd-148 and, U and Pu mass spectrometric method respectively. The isotope compositions of these elements, after their separation from the fuel samples were measured by mass spectrometric. The content of the elements in the irradiated fuel ore determined by isotope dilution mass spectrometric method using $^{233}$ U, $^{242}$ Pu and $^{150}$ Nd as spikes. The content of plutonium in the irradiated fuel was expressed by the correlation with uranium isotopes. The correlations between isotope compositions themselves and the total and fractional burnup ore compared with those calculated from ORIGEN2 code.

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우라늄 동위원소의 분석과 활용에 대한 고찰 (A Review on Analysis of Natural Uranium Isotopes and Their Application)

  • 김영민
    • 자원환경지질
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    • 제56권5호
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    • pp.547-555
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    • 2023
  • 분석 기기의 발달과 더불어 자연 우라늄 동위원소 비(238U/235U)와 분별작용에 대한 연구가 점차 증가하고 있다. MC-ICP-MS을 이용한 우라늄 동위원소의 정밀한 분석이 가능해지면서 137.88의 고정된 값으로 여겨졌던 자연 물질의 238U/235U 비가 우라늄 동위원소 분별작용에 의해 최대 수 퍼밀까지 변화할 수 있다는 것이 밝혀졌다. 본 고찰에서는 우라늄 동위원소의 분석과 표기에 대해 간략하게 설명한 후, 지구 상 주요 물질들의 우라늄 동위원소 값(δ238U)의 변화와 지구화학적 특징을 살펴본다. 특히, 우라늄 광상의 유형과 특징에 따른 우라늄 동위원소 조성 연구 사례를 소개하고, 상대적으로 큰 δ238U 범위를 야기하는 우라늄 동위원소 분별작용에 대해 논의한다. 이를 바탕으로 고준위 방사성 폐기물 처분장의 모의 실험을 위한 자연 유사 모델로서 우라늄 광상이 갖는 연구 의의에 대해 고찰한다.

Geochemical and S isotopic studies of pollutant evolution in groundwater after acid in situ leaching in a uranium mine area in Xinjiang

  • Zhenzhong Liu;Kaixuan Tan;Chunguang Li;Yongmei Li;Chong Zhang;Jing Song;Longcheng Liu
    • 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.

RESRAD-RECYCLE 전산코드를 활용한 금속폐기물 내 우라늄 자체처분 허용농도 예비 평가 (Preliminary Evaluation of Clearance Level of Uranium in Metal Waste Using the RESRAD-RECYCLE Code)

  • 이선우;홍정환;박정석;김광표
    • 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.

마이크로파 용해장치를 활용한 토양 중 우라늄의 알파분광분석법 (Efficient Sample Digestion Method for Uranium Determination in Soil using Microwave Digestion for Alpha Spectrometry)

  • 김창종;조윤해;김대지;채정석;윤주용
    • Journal of Radiation Protection and Research
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    • 제37권4호
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    • pp.213-218
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    • 2012
  • 토양 중 우라늄 동위원소의 분석을 위해서 알파분광분석법이 보편적으로 사용되고 있다. 다수의 토양시료를 분석할 경우 시료분해 시간을 단축함으로써 전체 분석시간을 효과적으로 줄일 수 있으며, 이를 위해 본 연구에서는 단시간에 시료를 완전 분해할 수 있는 마이크로파 용해장치를 활용하였다. IAEA-375를 분석 대상 토양으로 하여 용해되지 않은 시료의 양과 분석한 $^{234}U$$^{238}U$의 방사능 농도 값을 통해 시료분해 방법을 최적화 하였으며, 0.5 g의 토양시료에 최소 3 ml의 불산을 가했을 때 80분 내에 효과적으로 분해되는 것을 확인하였다. 이는 2~3일의 분해시간이 필요한 통상적인 방법(open vessel 및 closed vessel을 이용하는 방법)에 비해 시간을 단축 할 수 있어 효율적이며, 불산 사용을 최소화 하여 시료용해 시 발생할 수 있는 유해 물질의 발생 및 접촉을 줄일 수 있다는 장점이 있다.

Correlations between Zirconium Isotopes and Burnup Parameters in PWR Spent Nuclear Fuels

  • Kim, Jung-Suk;Chun, Young-Shin;Lee, Chang heon;Kim, Won-Ho;Eom, Tae-Yun
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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    • pp.551-556
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    • 1998
  • The correlation of isotope composition of Zr with the turnup and some heavy isotopes in PWR uranium dioxide fuel has been investigated. The total and partial ($^{235}$ U) burnup were determined by $^{148Nd}$ and by U and Pu mass spectrometric method, respectively. After separating Zr from the fuel samples, its isotope composition was measured by mass spectrometry. In addition, the quantities of the U and Pu in the spent fuel were determined by isotope di lution mass spectrometric method using $^{233}$ U and $^{242}$ Pu as spikes. The content of some heavy isotopes, $^{235}$ U, $^{239}$ Pu and $^{241}$ Pu, and the Pu Contribution to total turnup were expressed by the correlation with Zr isotope ratios, $^{91}$ Zr/$^{96}$ Zr and $^{93}$ Zr/$^{96}$ Zr The correlations by isotope compositions measured were compared wi th those calculated from ORIGEN2 code.

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$^{244}Pu$ + $^{136}Xe$ 반응에서 생성된 Pu, Np 및 U에 관한 연군 (Studies on Plutonium, Neptunium, and Uranium Produced in the /$^{244}Pu$ + $^{136}Xe$ Reaction)

  • Won Mok Jae
    • Nuclear Engineering and Technology
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    • 제13권3호
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    • pp.139-144
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    • 1981
  • Pu-244와 Xe-136반응에서 생성된 Pu, Np 및 U을 분리하여 그 핵반응 단면적을 측정하였다. 핵반응단면적은 각각 $\sigma$($^{245}$ Pu)=66 mb, $\sigma$($^{243}$ Pu)=57 mb, $\sigma$($^{246}$ Pu)=6.0 mb, $\sigma$($^{239}$ Np)=15 mb, $\sigma$($^{240}$ U)=12 mb, $\sigma$($^{241}$ U)=6.4 mb이었다.

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