• 분석과학
• /
• 제25권2호
• /
• pp.146-151
• /
• 2012

액체섬광계수기를 이용한 지하수 내 우라늄 동위원소의 최적 측정방법에 대한 연구를 수행하였다. 용매추출법을 이용해 우라늄을 추출하였고, 시료량과 pH에 따른 추출효율을 조사하였다. 우라늄 추출효율에 미치는 영향을 조사하기 위해 표준용액을 사용하여 100 mL~1 L 범위에서 시료량을 변화 시켰으며 pH는 0.5~10 범위에서 측정하였다. 실험결과 우라늄의 추출효율은 pH에 매우 민감한 것으로 나타났으며 pH 2 에서 최고치를 나타냈다. 이에 반해 시료량은 추출효율에 큰 영향을 미치지 않는 것으로 나타났다. 우라늄 표준시료를 이용한 실험 결과 추출효율은 $95.93{\pm}0.77%$ 이었고, 계측시간 5시간을 기준으로 한 우라늄의 검출한계는 0.018 Bq/L 이었다. 본 연구결과로부터 지하수에 함유된 우라늄의 최적추출 및 측정법을 확립할 수 있었고 본 방법의 검증을 위해서 지하수 중 우라늄의 분석에 일반적으로 사용되는 ICP-MS 측정결과와의 비교분석도 함께 수행하였다. 본 연구에서 개발된 분석법을 대전 주변 지역 네 곳의 지하수를 대상으로 우라늄 함량 및 동위원소 비의 측정에 적용한 결과 우라늄의 농도는 0.59~6.69 Bq/L 그리고 $^{234}U/^{238}U$의 방사성 비는 0.88~1.40 범위로 나타내었다.

• 한국동물학회지
• /
• 제37권4호
• /
• pp.565-572
• /
• 1994

연두금파리의 유충-번데기-성충의 발생에 따른 cyclic AMP(CAMP)와 ecdysteroids의 농도 및 cyclic AMP-dependent protein kinase(PKA)의 활성도를 High Performance Liquid Chromatography(HPLC)와 Liquid Scintillation Counter(LSC)를 이용하여 측정하고 상관 기능 변화를 조사하였다. CAMP의 농도와 PKA의 활성도는 종령유충 및 성충에서 낮은 갓(0.29 UM/g, 5.52~5.59 unit/mg)을 나타내었고 번데기 0일(0.49 UM/g. 92.22 unit/mg)과 7일(0.50UM/g, 24.45 unit/mg)에서 최고치를 보였으며 번데기 4일에서 최저수준(0.13 $\mu$M/g3.23 unit/mg)을 나타내었다. Ecdysone 농도는 번데기 2일에 최고치(37 84 USlg)를 4일에 최저치(18.46 Ugyg)를 보인 후, 5일에 24.37 1519로 상승하였으며 성충에서는 낮은 값을 나타내었다 그러나 20-hydroxvecdysone 농도는 번데기 4일(23.66 UgyS)과 번데기 6일(14.90 Ugyg)에 최고치를 이루었고, 7일에서 최저치(1.21 USi9)를 나타내었다.

• Nuclear Engineering and Technology
• /
• 제53권11호
• /
• pp.3717-3722
• /
• 2021

In this study, the recovery rates of the dissolution method for radioactivity analysis of expandable polystyrene (EPS) with a liquid scintillation counter (LSC) using tetrahydrofuran (THF), toluene, and acetone as solvents were estimated. The detection efficiency calibration curve for each solvent was derived. Two methods-the volumetric ratio method and the quenching agent method-were used to prepare quench source sets, and calibration curves were derived by linking the data from the two quench source sets. The R² value of the calibration curve for THF was found to be 0.984. The relationship between the mass of dissolved EPS and the quench level was estimated: the quench level increased as the mass of dissolved EPS increased. Premix and postmix dissolution methods were tested. The recovery rates using THF with the premix method were 84.9 ± 0.9% and 96.5 ± 1.5% for ³H and ¹⁴C, respectively. Furthermore, the stability of the recovery rate over time when using THF was evaluated. The dissolution method with the premixed solution exhibited a more stable recovery rate over time. The dissolution methods were found to be applicable for analysis using LSC, and THF was found to be the most suitable solvent for the proposed method.

• Nuclear Engineering and Technology
• /
• 제54권2호
• /
• pp.469-478
• /
• 2022

Tritium was extracted from tritium-contaminated aluminum samples by heating it in a high-temperature furnace at 200, 300, or 400 ℃ for 15 h. The extracted tritium was analyzed by using a liquid scintillation counter (LSC); the sample thicknesses were 0.4 and 2 mm. The differences in tritium extraction over time were also investigated by cutting aluminum stick samples into several pieces (1, 5, 10, and 15) with the same thickness, and subsequently heating them. The results revealed that there are most of the hydrated material based on tritium on the surface of aluminum. When the temperature was increased from 200 or 300 ℃-400 ℃, there are no large differences in the heating duration required for the radioactivity concentration to be lower than the MDA value. Additionally, at the same thickness, because the surface of aluminum is only contaminated to tritiated water, cutting the aluminum samples into several pieces (5, 10, and 15) did not have a substantial effect on the tritium extraction fraction at any of the applied heating temperatures (200, 300, or 400 ℃). The proportion of each tritium-release materials (aluminum hydrate based on tritium) were investigated via diverse analyses (LSC, XRD, and SEM-EDS).

• Journal of Radiation Protection and Research
• /
• 제26권3호
• /
• pp.155-159
• /
• 2001

Beta radiation is measured for an environmental monitoring purpose or for an internal radiation exposure monitoring of nuclear power plant's worker. In korea, strontium 89 and strontium 90 is measured for an environmental monitoring purpose. Also tritium and carbon 14 contained in urine is measured for an internal radiation exposure monitoring of nuclear power plant's worker. Because above isotopes emits low energy beta radiations having a wide range of energy, very complicated isotope separation preprocess is needed. In this study, two mixed beta emitting isotopes are measured simultaneously using a liquid scintillation counter(LSC) and analyzed by using a developed statistical method. Banded least square method is used to analyze the mixed spectrum, and the goodness-of-fitness test is proposed. Test results show that the developed procedure can be very useful for analyzing a mixed beta emitting isotopes.

• 한국지하수토양환경학회지:지하수토양환경
• /
• 제17권2호
• /
• pp.22-27
• /
• 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.

• Journal of Radiation Protection and Research
• /
• 제45권3호
• /
• pp.142-146
• /
• 2020

Background: Tritium (³H) analysis in groundwater was difficult because of its low activity. Therefore, the electrolytic enrichment method was used. To improve the detection limit and for performing simple analysis, a high-volume counting vial with the available liquid scintillation counter (LSC) was investigated. Further, it was compared with a conventional 20-mL counting vial. Materials and Methods: The LSC with the electrolytic enrichment method was used ³H analysis in groundwater. A high-volume 145-mL counting vial was compared with a conventional 20-mL counting vial to determine the counting characteristics of different LSCs. Results and Discussion: When a Quantulus LSC was used, the counting window between channels 35 and 250 was used. The background count was approximately 1.86 cpm, and the counting efficiency increased from 8% to 40% depending on the mixing ratio of the volume of sample and cocktail solution. For LSC-LB7, the optimum counting window was between 1 and 4.9 keV, which was selected by the factory (Hitachi Aloka Medical Ltd., Japan) by considering quenching using a standard external gamma source. The background count of LSC-LB7 was approximately 3.60 ± 0.29 cpm when the 145-mL vial was used and 2.22 ± 0.17 cpm when the 20-mL vial was used. The minimum detectable activity (MDA) of the 20-mL vial was greater for LSC-LB7 than for Quantulus. The MDA with the 145-mL vial was improved to 0.3 Bq/L when compared with the value of 1.6 Bq/L for the 20-mL vial. Conclusion: The counting efficiency when using the 145-mL vial was 27%, whereas it was 18% when using the 20-mL vial. This difference can be attributed to the vial volume. The figure of merit (FOM) of the 145-mL vial was four times greater than that of the 20-mL vial because the volume of the former vial is approximately seven times greater than that of the latter. Further, the MDA for ³H decreased from 1.6 to 0.3 Bq/L. The counting efficiency and FOM of LSC-LB7 was slightly less than those of Quantulus when the 20-mL vial was used. The background counting rate of the Quantulus was lower than that of the LSC-LB7.

• 분석과학
• /
• 제28권5호
• /
• pp.353-360
• /
• 2015

지하수 중 라돈은 끓임으로서 쉽게 제거할 수 있다. 다양한 라돈 농도를 가진 13 개 지하수 시료를 이용하여 가열 시간과 온도를 변경시키며 라돈의 제거효율을 평가하였다. 지하수 시료는 Bladder 펌프를 이용하여 채수하였고 용존산소, 수소이온농도 등의 현장수질은 Flow cell을 이용하여 측정 하였다. 경과시간 및 수온 별로 분취한 시료의 라돈 농도는 액체섬광계수기(LSC)로 분석하였다. 실험결과, 온도가 높을수록 경과시간에 따른 지하수 중 라돈의 제거율도 높아지며 지하수 중 라돈의 초기농도가 높을수록 경과시간에 따른 지하수 중 라돈의 제거율은 낮아진다. 즉, 지하수 중 라돈의 농도가 높을수록 가열에 의한 라돈 제거 시 더 많은 시간과 에너지를 필요로 한다. 따라서 지하수 중 라돈 제거율은 주로 라돈초기농도, 가열온도, 그리고 가열시간에 의해 결정된다.

• Journal of Radiation Protection and Research
• /
• 제33권1호
• /
• pp.21-26
• /
• 2008

Activity가 20만 dpm인 고상 $^3H$ 표준선원을 사용하여 액체섬광계수기에 대한 교정을 수행할 경우 환경시료와는 Activity 및 Geometry 차이가 존재하고, 계측조건 차이로 인해 많은 불확실성이 존재할 수 있지만 이에 대한 연구결과가 없는 실정이다. 따라서 본 연구에서는 민감도분석을 통해 최적의 계측조건을 도출한 후 그 결과에 근거하여 Geometry 및 Activity 차이에 의한 영향을 정량적으로 평가하였고, 각 항목에 의한 영향이 나타날 경우 추가실험을 통해 원인을 규명하였다. 계측 결과에 대한 검증을 수행하기 위해 Chi-square test와 방사능오차분석을 수행하였고, 민감도분석 결과 본 연구에서 제안한 방법이 기존 방법에 비해 $1{\sim}3%$정도 오차가 감소하였다. 방사능오차분석 결과 Activity 차이에 의한 영향은 무시할 수 있었지만 Geometry 차이에 의한 영향이 크게 나타났고, 이에 대한 원인을 규명한 결과 비수용성인 플라스틱용기는 반사체 역할을 하였고, Activity가 높을수록 플라스틱에 의한 영향은 무시할 수 있었으며, 선원형태 차이에 의한 영향이 지배적인 것으로 나타났다.

• 한국물환경학회지
• /
• 제23권2호
• /
• pp.201-205
• /
• 2007

This paper reports the amount of $^{222}Rn$ and $^{238}U$ in 18 sites of ground water and 30 sites of surface water. The instrument used to count $^{222}Rn$ activity was the liquid scintillation counter (LSC) which could resolute ${\alpha}$ and ${\beta}$ radiations. And $^{238}U$ was analyzed by the inductively coupled plasma (ICP). Radon and Uranium were not detected in raw and treated water which were sampled in a water treatment plant. However, radon ($^{222}Rn$) was high concentration in ground water from Jeon-la, Gang-won. So was uranium ($^{238}U$) in case of ground water from Gang-won, Choong-chung. Radon ($^{222}Rn$) activities were detected less than 15 pCi/L at 5 sampling points, 15~300 pCi/L at 7 sampling points, 300~4000 pCi/L at 6 sampling points. However, Radon ($^{222}Rn$) activities of all ground water samples were less than 4,000 pCi/L, which was bellow American Alternative Maximum Contamination Level (AMCL). Uranium ($^{238}U$) concentrations were less than $0.1{\mu}g/L$ at 5 sampling points, from $0.1{\mu}g/L$ to $20{\mu}g/L$ at 13 sampling points. Uranium was not detected in about 30% of the whole samples, but the concentration ranged from relatively low to high concentrations depending on the sampling point. The minimum detectable activity (MDA) of radon was 15 pCi/L. and the detection limit of uranium was $0.1{\mu}g/L$.