• Title/Summary/Keyword: liquid scintillation counting

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The effect of liposomal cephalexin on the dry period treatment of bovine Staphylococcus aureus mastitis (젖소의 Staphylococcus aureus성 유방염에 대한 liposomal cephalexin 의 건유기 치료효과)

  • Shin, Jin-ho;Han, Hong-ryul
    • Korean Journal of Veterinary Research
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    • v.32 no.2
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    • pp.251-258
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    • 1992
  • Liposomal cephalexin was used m the dry period treatment of bovine mastitis due to Staphylococcus aureus. Liposomes were prepared by stable plurilamellar vesicle(SPLV) process. The shape and size of SPLVs were examined by transmission electron microscopy. The entrapping efficiency and stability of SPLVs were determined by high performance liquid chromatography or liquid scintillation counting. The size of SPLVs ranged from 0.1 to $4.01{\mu}m$ in diameter, with an entrapping efficiency of cephalexin of 25.8 %. The formulation of liposomal cephalexin was used for treatment were SPLV-entrapped cephalexin and free cephalexin with total cephalexin concentration of 250mg per quarters. All quarters were infused intramammarily at the end of lactation period by liposomal cephalexin, free cephalexin, or blank liposome with free cephalexin. The number of quarters cured by liposomal cephalexin(14/15 quarters, 93 %) was significantly higher than that by free cephalexin(7/15 quarters, 46%). or by blank liposome with free cephalexin(8/15 quarters, 53 % ) (p<0.05).

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Study of the determination of 226Ra in soil using liquid scintillation counter (액체섬광계수기를 이용한 토양 중 226Ra 분석 방법 연구)

  • Jung, Yoonhee;Kim, Hyuncheol;Chung, Kun Ho;Kang, Mun Ja
    • Analytical Science and Technology
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    • v.29 no.2
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    • pp.65-72
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    • 2016
  • This study presented an analytical method for detecting radium in soils using a liquid scintillation counter (LSC). The isotope 226Ra was extracted from soil using the fusion method and then separated from interfering radionuclides using the precipitation method. Radium was coprecipitated as sulfate salts with barium (Ba) and then converted into Ba(Ra)CO3, which is soluble in an acidic solution. The isotope 222Rn, the decay progeny of 226Ra, was trapped in a water immiscible cocktail and analyzed by LSC. The pulse shape analysis (PSA) level was estimated using 90Sr and 226Ra standard solutions. The figure of merit was the highest at PSA 80, while the alpha spillover was the lowest at PSA 80. The counting efficiency was 243 ± 2% in a glass vial. This analytical method was verified with International Atomic Energy Agency (IAEA) reference materials, including IAEA-312, IAEA-314, and IAEA-315. The recovery ranged from 60–82%, while the relative bias between the measured value and the recommended value was less than 10%. The minimum detectable activity was 2.1 Bq kg−1 with dry mass 1 g, the background count rate of 0.02 cpm, the recovery rate of 70% and counting time of 30 min.

A study of activity ratios of uranium isotope in the groundwater using liquid scintillation counter (액체섬광계수기를 이용한 지하수 내 우라늄 동위원소 측정법에 관한 연구)

  • Cho, Soo-Young;Song, Kyung-Sun;Lee, Kil-Yong;Yoon, Yoon-Yeol;Kim, Won-Baek;Ko, Kyung-Sok
    • Analytical Science and Technology
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    • v.25 no.2
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    • pp.146-151
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    • 2012
  • An analytical method was developed for the measurement of uranium isotope in ground water using the liquid scintillation counting technique. A LKB Wallac Quantulus 1220 liquid scintillation counter (LSC) equipped with pulse shape analyzer (PSA) and a solvent extraction method were used for the measurement of uranium isotope in ground water samples. The effect of solution volume on the extraction efficiency was evaluated for 100 to 1000 mL solutions using a NIST standard reference material (NIST SRM 4321C). The effect of groundwater pH on the extraction efficiency was also investigated for pH ranging from 0.5 to 10. It was found that the extraction efficiency had a strong dependence on pH showing a maximum at pH 2. In contrast, the effect of groundwater volume on the extraction efficiency was negligible in the range investigated. According to the method, the extraction efficiency of uranium isotopes was near 96% and the lower detection limit for uranium was 0.018 Bq/L with the counting time of 300 min. The result of this study was also verified by the conventional ICP-MS measurement. It is demonstrated that the suggested method is valuable to the determination of the optimum extraction and measurement conditions for uranium in ground water. The method was successfully applied to the ground water at four locations near the Daejeon province. It was found that the uranium content and the isotopic ratio of $^{234}U/^{238}U$ at the locations ranged 0.59~6.69 Bq/L and 0.72~1.40, respectively.

Optimization of $^{241}$Pu Analysis and Application to Environmental Samples

  • Lee, Myung-Ho;Park, Yong-Ho;Kim, Sang-Bok;Hong, Kwang-Hee;Lee, Chang-Woo
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05d
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    • pp.82-87
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    • 1996
  • An optimized method for determining beta-emitting $^{241}$ Pu in the presence of alpha-emitting nuclides was developed using a liquid scintillation counting system. PSA-level was setting using pulse-shape discrimination. The $^{241}$ Pu counting channel was adjusted for maximum value of FM using the $^{241}$ Pu standard source. The volume of scintillant was determined for the maximum value of counting efficiency. The optimized method of $^{241}$ Pu has been applied to environmental samples to measure concentration of $^{241}$ Pu in soils and mosses. Also it has been identified the origin of Pu deposited in Korea from the activity ratio $^{241}$ Pu / $^{239,240}$Pu.

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Optimization of $CO_2$ Direct Absorption Method for the Determination of Carbon-14 in Environmental Samples (환경시료중의 방사성탄소 측정을 위한 $CO_2$ 직접흡수법의 최적화 연구)

  • Cho, Soo-Young;Woo, Hyung-Joo;Chun, Sang-Ki
    • Journal of Radiation Protection and Research
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    • v.23 no.4
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    • pp.237-242
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    • 1998
  • The goal of this work was to optimize the liquid scintillation counting techniques for the determination of C-14 in environmental samples such as biological and air samples. Carbon-14 activities in most environmental samples were measured with direct $CO_2$ absorption method. The highest figure of merit was found through the variation of Carbosorb $E^{TM}$ and Permatluor $V^{TM}$ ratio, in the measurement windows. The best condition was 1:1 volume ratio. Average 2.35 g of $CO_2$ was reproducibly absorbed in the 20 ml mixture within 40 min. The counting efficiency determined by repeated analysis of NIST oxalic acid standard and the background count rate were measured to be $58.8{\pm}1.4%$ and $1.88{\pm}0.06\;cpm$, respectively in case of saturated solution. The correction curves of counting efficiency for partially saturated solutions and for saturated solutions with quenching were prepared, respectively. The overall uncertainty of the sample specific activity for near background levels was estimated to be about 7 % for 4 hours counting at 95 % confidence level. The long-term stability of samples has been checked for all the counting techniques over a two week periods, and no apparent change in counting efficiency and background level was found at that time.

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Active metabolites in rat bile after intravenous injection of [3H] pteroylglutamic acid (랫드에 있어서 [3H] pteroylglutamic acid 의 정맥주사후(靜脈注射後) 담즙중(膽汁中) 활성대사물(活性代謝物)에 관한 연구(硏究))

  • Shin, Ho-chul;Shimoda, Minoru;Kokue, Eiichi
    • Korean Journal of Veterinary Research
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    • v.33 no.4
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    • pp.605-609
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    • 1993
  • Active metabolites in rat bile after an intravenous injection of $[^3H]$ pteroylglutamic acid(PteGlu)were studies using high-performance liquid chromatography(HPLC). Predominant four radioactive metabolites and parent compound PteGlu were detected on the chromatogram of HPLC with liquid scintillation counting system. These metabolites were identified as tetrahydrofolate, 10-formyltetrahydrofolate, 5-methyltetrahydrofolate and para-aminobenzoyl glutamate. The identification of active folate metabolites was based on the consistency of retention time profiles and hydrodynamic voltammograms which were obtained by HPLC with the electrochemical detection system, and characteristics of UV absorbance spectra obtained by HPLC with photodiode array detection system.

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Copolymerization of Phenyl Acetylene with Styrene (Phenyl Acetylene과 Styrene의 共重合)

  • Hyung Chick Pyun;Jaerok Kim;Woong-Moo Lee
    • Journal of the Korean Chemical Society
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    • v.13 no.4
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    • pp.387-393
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    • 1969
  • Gamma-ray induced copolymerization of phenyl acetylene with styrene is compared with that of the Ziegler catalyzed. The reactivity of styrene is greater than that of phenyl acetylene in the gamma-ray induced polymerization but much less than that of phenyl acetylene in the Ziegler catalyzed. The resulting copolymer is identified by means of DTA and spectrophotometry. Further, the liquid scintillation counting of styrene-${\alpha}-C^{14}$clarified the relative composition of the copolymers.

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Radiocarbon Dating (방사성탄소연대측정)

  • Leigh, Hyeon-Ju;Hwang, Jin-Ju;Paek, Hyun-Ju
    • 보존과학연구
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    • s.23
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    • pp.197-214
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    • 2002
  • It is very important to determine the age of the Cultural Properties in archeology. In about 1950, W.F. Libby and a team of scientists at the University of Chicago developed the Radiocarbon Dating technique. Radiocarbon($^14$C) Dating is probably one of the most widely used and best known absolute dating methods. Radiocarbon ages are conventionally specified to the year 1950. This year is 0 BP year. BP is the initial of Before Present. The $^14$C within an organism is continually decaying into stable carbon isotopes. When $^14$C decays, it emits a $\beta$ - particle with an energy content of 156 KeV and becomes 14N. Only the $\beta$ - particle is detected by Liquid Scintillation Counting. $^14$C has a half life of 5730 years. It has been used to date samples as old as 50,000 years. Radiocarbon determinations can be obtained on organic material : wood, charcoal, shell, etc. The results of radiocarbon dating using Benzene Synthesizer and Liquid Scintillation Counter are KCP539 $4030\pm60$BP year, KCP540 $3980\pm60$BP year, KCP575 $4870\pm50$, KCP576 $100\pm50$BP year, KCP577 $130\pm50$BP yea and KCP578 $210\pm70$BP year.

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Determination of carbon-14 and tritium in a PWR spent nuclear fuel (PWR 사용후핵연료 중 탄소-14 및 트리튬 정량)

  • Kim, Jung Suk;Park, Soon Dal;Lee, Chang Hun;Song, Byong Chul;Jee, Kwang Yong
    • Analytical Science and Technology
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    • v.18 no.4
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    • pp.298-308
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    • 2005
  • The methods for determining C-14 and tritium contents in the spent nuclear fuel sample were developed. The carbon-14($^{14}CO_2$) released during the dissolution of the spent fuel sample and $CaCO_3$ ($CO_2$ carrier) with 8 M $HNO_3$ at $90^{\circ}C$ was collected in trap containing 1.5 M NaOH. The volatile radioactive iodine evolved when the spent fuel was dissolved, was trapped on to Ag-silicagel (Ag-impregnated silicagel) adsorbent in column which is connected to two NaOH traps. The solutions which contain tritium as HTO after fuel dissolution were decontaminated by deionization with a mixture of cation and anion exchange resins and inorganic ionexchangers. The amount of C-14 in the trap solutions and the HTO concentration in the resulting deionization water were then determined by liquid scintillation counting.