• Title/Summary/Keyword: LSC 방법

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Optimal Method of Radon Analysis in Groundwater using Ultra Low-Level Liquid Scintillation Counter (극 저준위 액체섬광계수기를 이용한 지하수 중 라돈($^{222}Rn$) 측정법 연구)

  • Kim Yong-Je;Cho Soo-Young;Yoon Yoon-Yeol;Lee Kil-Yong
    • Journal of Soil and Groundwater Environment
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    • v.11 no.5
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    • pp.59-66
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    • 2006
  • Optimal method of radon analysis in groundwater was studied using ultra low-level liquid scintillation counter (ULLLSC) which is well known as an analytical instrument for analyzing the alpha and beta radionuclides in environmental materials. Optimization of pulse shape analyzer (PSA) in operating the LSC was performed with $^{241}Am\;and\;^{90}Sr/^{90}Y$ as well as $^{226}Ra$ Also, the chemical quenching of scintillation generation and the color quenching of the generated photon to photomultiplier tubes (PMT) were determined their effects not only to decrease the analytical efficiency but also to change the optimal PSA level and background due to high ion contents of groundwaters. The optimal PSA level was shown in the range of 90 to 110 with less than 5% error. The effects of high ion contents in groundwater for the analytical efficiency show within 10% error from the different ion contents. The chloroform as a quenching agent was used to determine the analytical efficiency with the different amount, showing that the efficiency decreases 20% using the 2% of chloroform.

시멘트 고화체 중 Sr-90 분석을 위한 시료 전처리

  • Pyo, Hyeong-Yeol;Kim, Yeong-Bok;Choe, Gwang-Sun;Han, Seon-Ho;Song, Gyu-Seok
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2009.11a
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    • pp.131-132
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    • 2009
  • 시멘트 고화체 중의 Sr-90 분석을 위한 시료 전처리 방법을 실험을 통하여 확립하였다. 시멘트 고화체 중의 Sr-90 과 같은 베타방출 핵종을 분석하기 위해서는 고화체 시료를 건조, 분쇄, 산처리, Sr-90 분리 및 LSC 를 이용한 Sr-90의 방사능 측정을 해야 한다. 이를 위하여 인수 고화체 시료를 전 처리 하기 전, SRM 1887a portland cement 를 사용하여 여러 산 처리 방법을 통하여 각 원소들의 회수율을 알아보았다. SRM 시료를 통하여 얻은 조건을 참조하여 실제 고화체 시료 5g 씩 3회의 7개 시료들을 전 처리하여 ICP-AES 를 통하여 각 원소들의 회수율을 비교하였다. 또한, 전처리 후 Sr 분리에 Sr-resin (Eichrom)를 이용하기 위해서는 Sr-resin 사용 시 많은 영향을 주는 칼슘의 량을 미리 알아야 한다, 이를 위하여 시멘트 고화체 중 50% 가까이 함유되어 있는 칼슘 량을 반 정량적으로 알아내기 위한 방법을 확립하였다.

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Evaluation of 226Ra analysis methods using a gamma-ray spectrometer and a liquid scintillation counter (감마선분광분석기와 액체섬광계수기를 이용한 226Ra 분석법 비교 연구)

  • Ju, Byoung Kyu;Kim, Moon Su;Kim, Hyun Koo;Kim, Dong Su;Cho, Sung Jin;Yang, Jae Ha;Park, Sun Hwa;Kim, Hyoung Seop;Kwon, Oh Sang;Kim, Tae Seung
    • Analytical Science and Technology
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    • v.28 no.3
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    • pp.228-235
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    • 2015
  • The efficiency and applicability of the solid phase extraction disk method in a 226Ra analysis were examined by the gamma ray spectrometer (GRS) method using a Marinelli beaker and the liquid scintillation counter (LSC) method for groundwater. The recovered 226Ra, which was filtered by the solid phase extraction disk, was analyzed using gamma ray spectrometer The disks, which were pretreated for caulking the daughter nuclide, were sealed with polyethylene film. Distilled water was used for the blank value of the 226Ra activity. The recovery values of 214Bi and 214Pb in the solid phase extraction disk, which used 226Ra standard material, were 80% (295.21 Kev) and 104% (351.92 Kev), respectively, which were higher than 75% determined by the LSC. The injection of nitrogen gas into the measuring chamber reduced the interference values by about 10%. The detection limits of the 226Ra activity in a blank sample of 5 L were 0.17~0.40 pCi/L after 80,000 seconds of measuring time. The relationship of the 226Ra activity in the solid phase extraction disk method and in the LSC method in seven groundwater samples showed a correlation coefficient value 0.987, which implies the applicability of the solid phase extraction disk method. The results showed that 226Ra activity in groundwater using the solid phase extraction disk method has the following benefits: simple pretreatment, time saving, high recovery values, a low detection limit, and so on. Compared with the LSC method and the GRS method using the Marinelli beaker for the 226Ra analysis, the solid phase extraction disk method could be useful in groundwater samples with low levels of activities of radionuclides because the method is not restricted by the volume of the sample.

A Study on the Variation of Rn-222 Concentration in Groundwater at Busan-Geumjeong area (부산 금정구지역의 지하수에 포함된 라돈농도 변화 연구)

  • Cho, Jungg-Sook;Lee, Hyo-Min;Kim, Sun-Woong;Kim, Jin-Seop
    • Journal of Radiation Protection and Research
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    • v.37 no.3
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    • pp.149-158
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    • 2012
  • In this paper, we measured the variations of radon concentrations in groundwater using low-level Liquid Scintillation Counter (LSC), an instrument for analyzing the alpha and beta radionuclides at its 10 sites around the Kumjung-Gu, north-western of Busan. Optimization of Pulse Shape Analyzer (PSA) to determinate the highest value of figure of merit (FM) was decided using Quantulus 1200 LSC with radium-226 source, the optimal PSA level was shown in the range of 100 to 110. The results show that the Minimum Detectable Activity (MDA) of radon concentrations is 0.61 $Bq{\cdot}L^{-1}$ for 20 minutes in PSA level. We find that the average radon concentration in groundwater is high in granitic rock area and low in volcanic rock area. (Biotite granite : 191.39 $Bq{\cdot}L^{-1}$, Micro graphic granite : 141.88 $Bq{\cdot}L^{-1}$, Adamellite : 92.94 $Bq{\cdot}L^{-1}$, Andesite (volcanic) : 35.35 $Bq{\cdot}L^{-1}$). No significant seasonal variation pattern is observed from the long-term variation analysis from 10 selected sites. We have not seen the significant correlation of radon concentration to groundwater temperature, atmospheric temperature, atmospheric pressure and rainfall. The concentration variation is probably caused by more complex factors and processes.

Simultaneous analysis method of 89Sr and 90Sr in liquid sample using automated separation system (자동핵종분리장치를 이용한 액체시료 중 89Sr, 90Sr 동시분석법 연구)

  • Kim, Heewon;Lee, Yong-Jin;Kim, Sun-Ha;Lee, Jin-Hong;Lim, Jong-Myoung;Kim, Hyuncheol
    • Analytical Science and Technology
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    • v.33 no.6
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    • pp.274-284
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    • 2020
  • This study described the analytical method for simultaneous determination of 89Sr and 90Sr in liquid sample using automated separation system. Radiostrontium in 0.5 kg of liquid sample was concentrated as SrCO3 to reduce the volume of sample, and purified from the sample using Sr-resin 2 mL (BV, Bed volume). The behavior of Sr and interferences such as Ba, Ca and Y were estimated with various flow rate ranging from 1 to 4 mL min-1. The detailed procedure for the purification of Sr on Sr-resin was presented. The purified radiostronitum was measured in Cerenkov mode and then measured in Scintillation mode by mixing scintillation cocktail. The measured value in both modes were used to calculate the activity of 89Sr and 90Sr. The performance tests were carried out the lab-control-sample having various activity ratio of between 89Sr and 90Sr. The recovery of Sr was ranged from 68 to 94 %. The relative bias of 89Sr activity was ranged from -5 to 20 %, and it was ranged from -10 to 10 % for 90Sr.

A Preliminary Study for the Analytical Method and Environmental Characteristics of Radium-226 in Groundwater (지하수 중 라듐-226의 분석방법 및 환경 특성에 관한 예비 연구)

  • Jeong, Do-Hwan;Kim, Moon--Su;Noh, Hoe-Jung;Yoon, Yoon-Yeol;Kim, Dong-Soo;Lee, Young-Joon;Ju, Byoung-Kyu;Hong, Jung-Ki;Kim, Tae-Seung
    • Journal of Soil and Groundwater Environment
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    • v.17 no.2
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    • pp.22-27
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    • 2012
  • $^{226}Ra$ in groundwater could be analyzed by various methods. LSC (liquid scintillation counter) is used to measure its activity of Ba co-precipitates with Hisafe III scintillation cocktail solution. Counting efficiency was obtained using NIST $^{226}Ra$ standard solution in triplicate and calculated $^{226}Ra$ concentration using the efficiency values. $^{226}Ra$ values of 19 groundwaters having Gross-${\alpha}$ concentrations of more than 5 pCi/L ranged from ND (${\leq}$ 0.1 pCi/L) to 1.18 pCi/L. Geologic settings of the 19 areas are composed of granitic rocks of Pre-Cambrian and Jurassic and Cretaceous, gneiss (schist) of Pre-Cambrian, and volcanic rocks of Cretaceous. No relationship was shown among $^{226}Ra$ a concentrations and in-situ water quality data, and Gross-${\alpha}$, uranium, radon concentrations.

Developing a Reactive System from Scenario-Based Specification Model (시나리오 기반 명세 모델로부터 반응형 시스템 개발)

  • Kwon, Ryoung-Kwo;Kim, Sung-Hae;Kwon, Gi-Hwon
    • Proceedings of the Korean Information Science Society Conference
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    • 2011.06b
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    • pp.200-203
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    • 2011
  • 다수의 모듈로 구성된 반응형 시스템을 개발하기 위해 외부의 입력 및 모듈간의 상호작용을 분석하는 것은 중요하고 어려운 문제이며, 반응형 시스템이 요구 사항을 올바르게 만족하는지를 확인하기 위해서는 많은 시간과 비용이 소모가 된다. 본 논문에서는 요구 사항을 LSC(Live Sequence Chart)를 이용해 시나리오 기반 명세 모델을 만들고 Synthesis를 통해 요구 사항을 모두 올바르게 만족하는 시스템 모델을 자동으로 생성한다. 궁극적으로 올바른 시스템 모델로부터 의미적으로 동일한 코드로 변환하는 과정을 보이는 것으로 시나리오 기반 명세 모델로부터 반응형 시스템을 개발하는 방법을 제안한다.

LSC를 이용한 지하수중의 H-3 측정연구

  • Yun Yun-Yeol;Jo Su-Yeong;Lee Gil-Yong;Kim Yong-Je
    • Proceedings of the Korean Society of Soil and Groundwater Environment Conference
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    • 2006.04a
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    • pp.286-288
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    • 2006
  • 삼중수소는 물분자중 수소원소의 동위원소로서 물의 유동연구에 가장 이상적인 추적자로서 활용된다. 이러한 삼중수소 분석결과는 지표수 지하수 상관관계 해석 및 지하수의 연대측정등 수문학 연구의 중요한 자료로 활용되고 있다. 지하수 연구에 필요한 삼중수소의 측정법을 확립코자 극저준위 액체섬광계수기를 도입하였으며 NIST 표준시료를 사용하여 실험방법을 확립하였다. 삼중수소의 측정효율은 25.7 % 였으며, 전기분해법을 사용하지 않고 단순 분리법만을 사용하였을 경우 10 ml의 측정 시료와 섬광액으로 Ultima-Gold LLT를 사용하여 0.18 Bq(1.5 TU)의 검출한계를 얻었다.

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Effect Evaluation by Activity and Geometry Difference in Calibration on LSC (LSC 장비를 이용한 교정시 Activity 및 Geometry 차이에 의한 영향 평가)

  • Han, Sang-Jun;Lee, Kyung-Jin;Lee, Seung-Jin;Kim, Hee-Gang;Park, Eung-Seop
    • Journal of Radiation Protection and Research
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    • v.33 no.1
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    • pp.21-26
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    • 2008
  • When the calibration on Liquid Scintillation Counter using the Solid $^3H$ Standard Source of 200,000DPM is executed, the uncertainty due to activity and geometry difference, exists. Therefore, this paper intends to evaluate environmental samples comparatively accurately as decreasing this uncertainty existing in the process of calibration. For this, measurements on samples manufactured by $^3H$ Standard Source and sensitivity study were performed. Also, this paper verified calibration results using Radioactivity-Error-Analysis Method, and evaluated quantitatively the effect by geometry and activity difference based on verification result. According to the result of sensitivity study, in case of using the exposure time of 75 sec and Repeat method, the measuring accuracy and precision of about $1{\sim}3%$ were increased in comparison with the existing method. By analysis result, the effect by activity difference did not appear, and a plastic cell existing into Teflon vial made a role as reflector. The less the effect of plastic cells are decreased, the more activity is high, and the effect of those can be neglected at the activity of 200,000 DPM.

A Study on the Decontamination of Cs-137 and Sr-90 Contained in the Liquid Radioactive Waste Discharged from the Spent Fuel Storage Tank Using Microalgae (미세조류를 이용한 사용후핵연료 저장조에서 배출되는 방사성 폐액에 함유된 Cs-137 및 Sr-90 제염에 관한 연구)

  • Kim, Tae Young;Park, Hye Min;Song, Yang Soo;Lee, Un Jang
    • Resources Recycling
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    • v.31 no.5
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    • pp.20-25
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    • 2022
  • In this study, the applicability of microalgae was evaluated for eco-friendly decontamination of cesium-137 (Cs-137) and strontium-90 (Sr-90), which are radioactive nuclides contained in radioactive waste. The monolithic radioactive solution used in the experiment was manufactured at a concentration of 1.5 Bq/mL Cs-137 and 1.0 Bq/mL Sr-90 by diluting a standard radioactive solution and distilled water. This experiment used two types of microalgae, Chlorella Vulgaris was used for Sr-90 decontamination and Hematococcus pluvialis for Cs-137 decontamination. The experimental method is to put the microalgae cultured for 2 weeks into a bottle with a semi-permeable membrane, and then put the bottle in which the microalgae was put into the manufactured radioactive solution, so that the microalgae and the radioactive solution react through the semi-permeable membrane for 48 hours. For the radioactivity concentration analysis of each sample, a gamma-ray nuclide analyzer was used for Cs-137, a γ-ray isotope, and a Liquid Scintillation Count(LSC) was used f or Sr-90, a β-ray isotope. As a result of the experiment, it was confirmed that about 88.0 % of Cs-137 and about 89.7 % of Sr-90 could be decontaminated, and about 98.6 % of Sr-90 was finally able to be decontaminated by the two-stage decontamination method.