• Journal of Ginseng Research
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• 제17권2호
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• pp.114-122
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• 1993

0.5 mg of natural ginsenoside mixture and 0.8 $\mu$Ci of synthesized 14C-ginsenosides were administered orally to a rat and killed at one hour after the ginsenoside administration and the liver was fractionated into nuclear fraction, mitrochondria microsomes and cytosol fraction. Radioactivity distribu lion in subcellular fractions of the liver showed that 32o1c of total radioactivity absorbed in the liver was in cytosol fraction but a significant portion of the radioactivity was also found in mitochondria (26.6%) and microsomal fraction (18.l%). 5.8% of the total radioactivity was recovered from the nuclear fraction as well. This suggested that ginsenosides might be distributed into all subcellular fractions. Activities of mitochondrial aldehyde dehydrogenase, lactate dehydrogenase and malate dehydrogenase of the liver of rat at two hours after the ginsenoside administraion were found appreciably stimulated, suggesting that the ginsenoside concentration in the liver might be around 10-5%, since optimum concentrations for most enzyme catalyzed reactions in vitro were known to be 10-6% 10-4%. A significant portion of the radioactivity recovered from subcellular fractions of the liver was found in protein fractions, suggesting that proteins might interact with ginsenosides. Examination of protein-ginsenoside interation by gel filtration, equilibrium dialysis and amonium sulfate precipitation technique suggesting that proteins and ginsenosides do not bound covalently but weakl\ulcorner combined. When purified ginsenoside Rbl and Rgl were incubated with rat liver cytosolic enzymes for 20 min, the above ginsenosides were hydrolyzed quickly, suggesting that ginsenosides might be rapidly hydrolyzed and metabolized in the liver. It was also observed in vitro that the ginsenosides such as Rbl and Rgl were easily hydrolyzed by rat liver cytosol preparation suggesting that absorbed ginsenosides might be quickly hydrolyzed and metabolized in the liver.

• 한국환경농학회지
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• 제26권2호
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• pp.186-191
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• 2007

1998년부터 2006년까지 국내 방사능 교차분석에 참여하여 제주지역의 환경방사능 감시를 위한 방사능 분석 기술의 능력 검증과 신뢰도를 확보하기 위하여 수행되었다. 전베타 방사능 분석 시료는 공기부유진 필터와 물이었고, 감마 분석은 토양과 물 시료 중 자연 및 인공 방사성 핵종들이었다. 전베타 방사능 분석 값은 1998년과 1999년 물 시료를 제외하고는 모두 신뢰도 범위내의 값을 가졌고, 감마 핵종은 토양 시료 중의 $^{40}K$와 $137^{CS}$ 그리고 물 시료 중 몇 개의 핵종을 제외하고는 대부분 매우 우수한 평가를 받았다. 따라서 방사선 이상 사고시 원자력 안전을 위한 제주지역의 환경방사능 감시를 위한 신뢰도를 확보하여 자체적으로 환경방사능을 분석할 수 있는 능력을 함양하였다.

• International Journal of Contents
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• 제8권2호
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• pp.60-66
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• 2012

This study was designed to detect and measure the concentration of radioactivity of natural radionuclides ($^{238}U$, $^{232}Th$, $^{40}K$) and artificial radionuclides ($^{137}Cs$, $^{60}Co$) present in the drinking water of the city of Busan and surrounding areas in South Korea, and also to measure the absorbed dose of radiation caused by these elements in the residents so as to help better manage the risk that these radionuclides pose in the future. For the purposes of the study, a total of 42 samples of water were collected from three key water sources (19 samples of groundwater, 4 samples of tap water, and 19 samples of surface water) and their contents were analyzed for radioactivity concentration. The results revealed that two natural radionuclides, $^{238}U$ and $^{232}Th$, exist in the groundwater with an average concentration of radioactivity of 3.34 Bq/L and $8.28{\times}10^{-5}Bq/L$ respectively, while the surface water was found to contain the same two radionuclides with mean concentrations of 0.849 Bq/L and $1.103{\times}10^{-4}Bq/L$ respectively. In addition, of the 19 samples of the groundwater, $^{137}Cs$ was found in eight of them and $^{60}Co$ was detected in ten. Of the four samples of the tap water, $^{137}Cs$ was detected in all samples and $^{60}Co$ was detected in three. Both $^{137}Cs$ and $^{60}Co$ were detected in all 12 samples of surface water. As far as $^{40}K$ is concerned, this element was detected in three of the 19 groundwater samples, but was not detected in any surface or tap water sample. In addition, the absorbed dose of $^{238}U$ from the groundwater was $7.94{\times}10^{-8}Sv/y$, while the absorbed dose of $^{232}Th$ from the surface water was $9.33{\times}10^{-13}Sv/y$. The absorbed dose of $^{137}Cs$ from the tap water was $7.33{\times}10^{-5}Sv/y$, while the absorbed dose of $^{60}Co$ from the surface water was the highest at $4.23{\times}10^{-6}Sv/y$.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1289-1296
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• 2020

The estimation of radioactivity level is vital for population health risk assessment and geological point of view and can be evaluated as rate of exhalation and source concentration (²²⁶Ra, ²³²Th and ⁴⁰K). The present study deals with the soil samples for investigation of radionuclides content and exhalation rates of radon -thoron gas from different sites in northern Haryana, India. Absorbed dose and associated index estimated in the present study are the measures of environmental radioactivity to inhalation dose. Effective doses received by different tissues and organs by considering different occupancy and conditions are also measured. Exhalation rates of radon and thoron are measured with active scintillation monitors based on alpha spectroscopy namely scintillation radon (SRM) and thoron (STM) monitors respectively. Sample height was optimized before measurement of thoron exhalation rate using STM. Average values of radon and thoron exhalation are found 16.6 ± 0.7 mBqkg^-1h^-1 and 132.1 ± 2.6 mBqm^-2s^-1 respectively. Also, a simple approach was also adopted, to evaluate the thoron exhalation which accomplished a lot of challenges, the results are compared with the data obtained experimentally. The study is useful in the nationwide mapping of radon and thoron exhalation rates for understanding the environmental radioactivity status.

• Journal of Ginseng Research
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• 제10권1호
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• pp.108-113
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• 1986

인삼(Panax ginseng C. A. Meyer)뿌리 절편을 효소원으로 사용하여 $^14C$-acetate로부터 제조한 방사성 인삼사포닌을 함유한 인삼 사포닌 분획 조제물을 High performance liquid chromatography방법으로 분리하여 각 glycosides의 함량과 비 방사능을 측정하였다. 1mg의 $^14C$-표지사포닌을 함유한 인삼 사포닌을 쥐에게 구경 투여하고 1시간후 혈청 및 간장으로부터의 추출물을 분석한 결과 혈청이나 간의 경우 모두 사포닌 투여후 회수된 매탄올-물층의 방사능이 빠른 속도로 경감되었으나 방사능이 어느 수준 이하가 되면 방사능 소멸속도가 크게 저하되는 것으로 보아 일정수준의 인삼사포닌은 비교적 오래 혈청이나 간에 잠재하는 것으로 사료된다. 각 glycosides에 따라 흡수정도는 다르나 0.1%-1%정도 흡수된 것으로 확인되었고 간에서의 인삼 사포닌의 농도는 인삼 사포닌 투여후 상당기간 $10^{-6}$%-$10^{-5}$%수준을 유지할 것으로 예상된다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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• pp.464-469
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• 1998

A coincidence gamma-ray spectroscopy method was applied to reduce the background radioactivity for measuring the activity of radioisotopes in a sample in the presence of environmental natural radioactivity. A HPGe detector was used for the coincident spectrum as a main detector and a NaI(Tl) scintillation detector for gating purposes as an associated detector. For coincidence spectroscopy the whole energy spectrum of associated detector was used instead of gate signals. The coincident events obtained from the gating spectrum was evaluated by a coincidence computer program in this study instead of timing circuit. In this work, the background of detection environment was reduced to factor 100 and peaks to be determined was reduced to factor 30 using the coincidence gamma-ray spectroscopy.

• 한국방사선학회논문지
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• 제8권6호
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• pp.293-299
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• 2014

Compton suppression 장치는 Compton 산란 반응을 이용하여, 스펙트럼의 Compton continuum 부분을 억제함으로써 Compton continuum 영역 내에서의 감마선 피크들의 분석을 보다 명확하게 할 수 있게 해주는 장치이다. 표층토양 시료에서 검출된 인공 방사능인 $^{137}Cs$과 자연 방사능인 $^{40}K$핵종의 방사능 농도 값들에 대한 방사능 계수치가 백그라운드를 상회하는 측정값이 발생되거나, 불필요한 방해피크나 비해석 대상 피크에 대하여 검출된 표준선원의 방사능 농도 값들의 실측치에 대한 background를 비억제 스펙트럼(Compton Unsuppression)과 억제 스펙트럼(Compton suppression)을 적용시켜 측정 에너지에 대한 교정을 알고자 점선원인 $^{137}Cs$을 거리별에 따라 측정하여, 몬테칼로 시뮬레이션과 비교 분석함으로서 효율적인 검출 능력을 얻고자 함이며, Compton 억제 인자를 보면 거리가 멀어짐에 따라 CSF 값이 클수록 더 많은 Compton suppression가 이루어졌음을 알 수 있고, $^{137}Cs$을 이용한 컴프턴 비억제 모드와 억제모드로 측정된 스펙트럼에서 컴프턴 연속에 의한 백그라운드가 감소함을 알 수 있었다.

• Journal of Radiation Protection and Research
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• 제42권1호
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• pp.33-41
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• 2017

Background: Phosphate rock and its by-product are widely used in various industries to produce phosphoric acid, gypsum, gypsum board, and fertilizer. Owing to its high level of natural radioactive nuclides (e.g., $^{238}U$ and $^{226}Ra$), the radiological safety of workers who work with phosphate rock should be systematically managed. In this study, $^{238}U$, $^{232}Th$, $^{226}Ra$, and $^{40}K$ levels were measured to analyze the transport characteristics of these radionuclides in the production cycle of phosphate rock. Materials and Methods: Energy dispersive X-ray fluorescence and gamma spectrometry were used to determine the activity of $^{238}U$, $^{232}Th$, $^{226}Ra$, and $^{40}K$. To evaluate the extent of secular disequilibrium, the analytical results were compared using statistical methods. Finally, the distribution of radioactivity across different stages of the phosphate rock production cycle was evaluated. Results and Discussion: The concentration ratios of $^{226}Ra$ and $^{238}U$ in phosphate rock were close to 1.0, while those found in gypsum and fertilizer were extremely different, reflecting disequilibrium after the chemical reaction process. The nuclide with the highest activity level in the production cycle of phosphate rock was $^{40}K$, and the median $^{40}K$ activity was $8.972Bq{\cdot}g^{-1}$ and $1.496Bq{\cdot}g^{-1}$, respectively. For the $^{238}U$ series, the activity of $^{238}U$ and $^{226}Ra$ was greatest in phosphate rock, and the distribution of activity values clearly showed the transport characteristics of the radionuclides, both for the byproducts of the decay sequences and for their final products. Conclusion: Although the activity of $^{40}K$ in k-related fertilizer was relatively high, it made a relatively low contribution to the total radiological effect. However, the activity levels of $^{226}Ra$ and $^{238}U$ in phosphate rock were found to be relatively high, near the upper end of the acceptable limits. Therefore, it is necessary to systematically manage the radiological safety of workers engaged in phosphate rock processing.

• Nuclear Engineering and Technology
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• 제54권4호
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• pp.1431-1438
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• 2022

In this study, natural radioactivity concentrations and dosimetric values of fly ash samples were evaluated for the landfill area of the coal-fired power plant (CFPP) complex at Binh Thuan, Vietnam. The average activity concentrations of ²³⁸U, ²²⁶Ra, ²³²Th and ⁴⁰K were 93, 77, 92 and 938 Bq kg^-1, respectively. The average results for radon dose, indoor external, internal, and total effective dose equivalent (TEDE) were 5.27, 1.22, 0.16, and 6.65 mSv y^-1, respectively. The average emanation fraction for fly ash were 0.028. The excess lifetime cancer risks (ELCR) were recorded as 20.30×10^-3, 4.26×10^-3, 0.62×10^-3, and 25.61×10^-3 for radon, indoor, outdoor exposures, and total ELCR, respectively. The results indicated that the cover of shielding materials above the landfill area significantly decreased the gamma radiation from the ash and slag in the ascending order: Zeolite < PVC < Soil < Concrete. Total dose of all radionuclides in the landfill site reached its peak at 19.8 years. The obtained data are useful for evaluation of radiation safety when fly ash is used for building material as well as the radiation risk and the overload of the landfill area from operation of these plants for population and workers.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4253-4264
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• 2022

Since the implementation of the phosphate project in Bled El-Hadba (BEH) deposit, western region of Tébessa, no detailed study has been conducted to assess the natural radioactivity distribution and the associated radiological risk parameter for this open-pit mine. For the sake of determining a credible premining reference database for the region of interest, 21 samples were collected from different geological layers of the above-mentioned deposit. Gamma Spectrometry was applied for measuring radioactivity using a high resolution HPGe semiconductor detector. The obtained activity results have shown a significant broad variation in the radioactive contents for the different phosphate samples. The total average concentrations (in Bq·kg^-1) for ²²⁶Ra, ²³⁸U, ²³⁵U, ²³²Th and ⁴⁰K computed for the different type of phosphate layers were found to be 570 ± 169, 788 ± 280, 52 ± 18, 66 ± 6 and 81 ± 18 respectively. The mean activity concentrations of the measured radionuclides were compared to other regional and worldwide deposits. The ratios between the detected radioisotopes have been calculated for spatial distribution of natural radionuclides in the study area. Based on the aforementioned activity concentrations, the corresponding radiation hazard parameters were assessed. Correlations between the obtained parameters were drawn and a multivariate statistical analysis (Pearson Correlation, Cluster and Factor analysis) was carried out in order to identify the existing relationships.