• Journal of the Korean Society of Radiology
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• v.8 no.6
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• pp.293-299
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• 2014

Compton suppression device is a device by using the Compton scattering reaction and suppress the Compton continuum portion of the spectrum, so can be made more clear analysis of gamma ray peak in the Compton continuum region. Measurements above background occurs or, radioactivity counts of radioactivity concentration value of $^{40}K$ nuclides $^{137}Cs$ and natural radioactivity artificial radioactivity detected from the surface soil sample, unwanted non-target analysis and interference peak who dotted line you know the calibration of the measurement energy is allowed to apply the (Compton suppression) non-suppressed spectrum inhibition spectrum and (Compton Unsuppression) the background to the measured value of the activity concentration value of the standard-ray source is detected relative to the peak of By measuring according to the different distances cause $^{137}Cs$, and comparative analysis of the Monte Carlo simulation, in order to obtain a detection capability for efficient, looking at the Compton inhibitor, as the CSF value increases with increase in the distance, more It was found that the background due to Compton continuum of the measured spectrum suppression mode Compton unrestrained mode can know that the Compton suppression many were made, using a $^{137}Cs$ is reduced.

• Nuclear Engineering and Technology
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• v.49 no.8
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• pp.1752-1757
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• 2017

The aim of this study is to evaluate the radioactivity levels and radiological impacts of representative black sand samples collected from different locations in the Rashid area, Egypt. These samples were prepared and then analyzed using the high-resolution gamma ray spectroscopy technique with a high-purity germanium detector. The activity concentration ($A_c$), minimum detectable activity, absorbed gamma dose rate, external hazard index ($H_{ex}$), annual effective dose rate equivalent, radium equivalent, as well as external and internal hazard index ($H_{ex}$ and $H_{in}$, respectively) were estimated based on the measured radionuclide concentration of the $^{238}U$($^{226}Ra$) and $^{232}Th$ decay chains and $^{40}K$. The activity concentrations of the $^{238}U$, $^{232}Th$ decay series and $^{40}K$ of these samples varied from $45.11{\pm}3.1Bq/kg$ to $252.38{\pm}34.3Bq/kg$, from $64.65{\pm}6.1Bq/kg$ to $579.84{\pm}53.1Bq/kg$, and from $403.36{\pm}20.8Bq/kg$ to $527.47{\pm}23.1Bq/kg$, respectively. The activity concentration of $^{232}Th$ in Sample 1 has the highest value compared to the other samples; this value is also higher than the worldwide mean range as reported by UNSCEAR 2000. The total absorbed gamma dose rate and the annual effective dose for these samples were found to vary from 81.19 nGy/h to 497.81 nGy/h and from $99.86{\mu}Sv/y$ to $612.31{\mu}Sv/y$, which are higher than the world average values of 59 nGy/h and $70{\mu}Sv/y$, respectively. The $H_{ex}$ values were also calculated to be 3.02, 0.47, 0.63, 0.87, 0.87, 0.51 and 0.91. It was found that the calculated value of $H_{ex}$ for Sample 1 is significantly higher than the international acceptable limit of <1. The results are tabulated, depicted, and discussed within national and international frameworks, levels, and approaches.

• Journal of Radiation Industry
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• v.18 no.3
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• pp.195-207
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• 2024

International organizations such as IAEA and EC recommend graded approach by identifying NORM industries requiring radiation protection. In Korea, single regulation rather than graded regulation for NORM industry is applied. Therefore, it consumes more manpower and costs than necessary for both regulators and workers, and is not optimized. The purpose of this study is to analyze domestic and foreign NORM industry regulatory standards and radiological characteristics for graded approach of NORM industry in Korea. Safety reports and publications such as SRS 49 and ICRP 142 published by international organizations were investigated, and domestic and foreign NORM regulatory guidelines and legislation such as Health Canada and the Act on Protective Action Guidelines Against Radiation in the Natural Environment were investigated to indicate NORM industries and regulatory standards. The radioactivity concentration of raw materials or by-products, radiation dose by industrial process of the NORM industry identified in IAEA and Korea were investigated. Nine NORM industries in Korea were identified based on the NORM industry from IAEA and KINS survey report. Foreign countries such as Canada, UK and Denmark were executing graded approach such as classification of dose level or licensing, registration, notification based on safety assessment. Radioactivity concentration of domestic and foreign NORM industries were widespread up to 200 Bq g^-1 or higher based on industrial process and work type, and numerous NORM industries that exceeded radiation dose of 1 mSv y^-1 were indicated. Therefore, it is necessary to consider handling materials and work types of identified NORM industry when establishing graded approach for NORM industry in Korea considering domestic situation. The results of this study are expected to be used as basic data for developing methodology of graded approach for NORM industry in Korea.

• International Journal of Contents
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• v.8 no.2
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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 $4.23{\times}10^{-6}Sv/y$.

• Analytical Science and Technology
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• v.33 no.4
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• pp.186-196
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• 2020

A simple and rapid preconcentration method of actinide from seawater using Actinide resin was developed and tested with the seawater spiked with a known U and Th. The developed method of Actinide resin based on column chromatography is less time-consuming and requires less labor compared with a typical co-precipitation technique for preconcentration of actinides. U and Th, which are relatively weak-bonded with Actinide resin among actinides, were used to determine the optimum flow rate of seawater sample and evaluate the capacity of Actinide resin to concentrate actinides from seawater. A flow rate of 50 mL min^-1 was available with Actinide resin 2 mL (BV, bed volume). When 5 or 10 L of seawater containing U were loaded on Actinide resin (2 mL, BV) at 50 mL min^-1, the recovery of U was 93 % and 86 %, respectively. For extraction of actinides bound with Actinide resin, we compared three methods: solvent extraction, ashing-acid digestion, and ashing-microwave digestion. Ashing-microwave digestion method shows the best performance of which is the recovery of 100 % for U and 81 % for Th. For the preconcentration of actinides in 200 L of seawater, a typical coprecipitation method requires 2-3 days, but the developed method in this study is achieved the high recovery of actinides within 12 h.

• Journal of Ginseng Research
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• v.17 no.2
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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.

• Nuclear Engineering and Technology
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• v.56 no.1
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• pp.207-215
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• 2024

This study focuses on measuring the levels of naturally occurring radioactivity in the soil of Swabi, Khyber Pakhtunkhwa, Pakistan, as well as the associated health hazard. Thirty (30) soil samples were collected from various locations and analyzed for ²²⁶Ra, ²³²Th, and ⁴⁰K radioactivity levels using a High Purity Germanium detector (HPGe) gamma-ray spectrometer with a photo-peak efficiency of approximately 52.3%. The average values obtained for these radionuclides are 35.6 ± 5.7 Bqkg^-1, 47 ± 12.5 Bqkg^-1, and 877 ± 153 Bqkg^-1, respectively. The level of ²³²Th is slightly higher and ⁴⁰K is 2.2 times higher than the internationally recommended limit of 30 Bqkg^-1 and 400 Bqkg^-1, respectively. Various parameters were calculated based on the results obtained, including Radium Equivalent (Ra_eq), External Hazard (H_ex), Absorbed Dose Rate (D), Annual Gonadal Equivalent Dose (AGDE), Annual Effective Dose Rate, and Excess Lifetime Cancer Risk (ELCR), which are 170.3 ± 24 Bqkg^-1, 0.46 ± 0.06 Bqkg^-1, 81.4 ± 2.04 nGy h^-1, 582 ± 78.08 µSvy^-1, 99.8 ± 13.5 µSv Gy^-1, and 0.349 ± 0.04, respectively. These values are below the limits recommended by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) in 2002. This study highlights the potential radiation threats associated with natural radioactivity levels in the soil of Swabi and provides valuable information for public health and safety.

• YAKHAK HOEJI
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• v.41 no.6
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• pp.737-748
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• 1997

Distribution of rhEGF in the skin, plasma and several organ tissues following topical application of $^{125}I-rhEGF$ (0.4${\mu}$Ci) solution in 25% Pluronic F-127 on 154$mm^2$ normal and damaged (burned and stripped) skins of hairless mice was examined. The radioactivity in the stripped skin tissues increased as a function of time, and was 10-20 times higher than that in the normal and burned skins. The fractions of intact drug in the skin tissues were 40-60% for the normal and burned skins, and 60-80% for the stripped skin. It indicates that the stratum corneum layer behaves as a barrier for the dermal penetration of the drug. The radioactivity in the plasma was much higher for the stripped skin than for the normal and burned skins. However, the concentration of intact drug in the stripped skin was comparable to those in the normal and burned skins indicating most severe degradation (or metabolism) of the drug in the stripped skin. As a result, the fraction of intact drug in the plasma was lowest for the stripped skin (<10%). Body organ distribution of the drug was much higher for the stripped skin. The concentration in the stomach. Both in total radioactivity and intact drug, showed more than 10-times higher value than in the other organs (liver, kidney and spleen). The fraction of intact drug in each organ tissue was below 10-20%. And generally lowest for the stripped skin. The lowest fraction of the drug for the stripped skin could not be explained by the activity of the aminopeptidases in the skin since it was lower for the stripped skin than for the normal skin. Thereover, the fraction of intact drug appears to be determined by the balance between dermal uptake and systemic elimination of the drug, for example. The mechanism of dermal uptake of rhEGF was examined by topical applying 200${\mu}$l of 25% Pluronic F-127 solution containing 0.4 ${\mu}$Ci of $^{125}I-rhEGF$ and 0.14${\mu}$Ci of $^{14}C$-inulin (a marker of passive diffusion). The radioactivity of $^{125}I-rhEGF$ at each sampling time point (0.5, 1, 2, 4 and 8hr) was correlated (p<0.05) with the corresponding radioactivity of $^{14}C$-inulin. It appears to indicate the rhEGF may be uptaken into the skins mainly by the passive diffusion. This hypothesis was supported by the constant specific binding of EGF to the skin homogenates regardless of the skin models. Receptor mediated endocytosis (RME) appears to contribute negligibly, if any, to the overall uptake process.

• Journal of radiological science and technology
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• v.44 no.6
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• pp.645-653
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• 2021

With the recent development of precision medicine(Theranostics), interest and utilization of the quantitative function of SPECT/CT are increasing. This study aims to investigate the effect on the radioactivity concentration estimate by the increase or decrease in the total time of SPECT/CT imaging conditions. A standard image was obtained by the conditions of a total acquisition time of 600 sec(10 sec/f × 120 frames) by diluting ^99mTc 91.76 MBq in a cylindrical phantom filled with sterile water, and a comparative image was obtained by increasing the total acquisition time by -90%, -75%, -50%, -25%, +50%, +100%. The CNR, radioactive concentration estimate(cps/ml), and the variation rate(%) of the recovery coefficient(RC) were analyzed by measuring the overall coefficient of interest in each image. The results[CNR, Radiation Concentration, RC] by the change in the number of projections for each increase or decrease rate(-90%, -75%, -50%, -25%, +50%, +100%) of total acquisition time are as follows. [-89.5%, +3.90%, 1.04] at -90%, [-77.9%, +2.71%, 1.03] at -75%, [-55.6%, +1.85%, 1.02] at -50%, [-33.6%, +1.37%, 1.01] at -25%, [-33.7%, +0.71%, 1.01] at +50%, [+93.2%, +0.32%, 1.00] at +100%. and also The results[CNR, Radiation Concentration, RC] by the acquisition time change for each increase or decrease rate(-90%, -75%, -50%, -25%, +50%, +100%) of total acquisition time are as follows. [-89.3%, -3.55%, 0.96] at -90%, [-73.4%, -0.17%, 1.00] at -75%, [-49.6%, -0.34%, 1.00] at -50%, [-24.9%, 0.03%, 1.00] at -25%, [+49.3%, -0.04%, 1.00] at +50%, [+99.0%, +0.11%, 1.00] at +100%. Image quality(CNR) showed a pattern of change in proportion to the increase or decrease in the total acquisition time of SPECT/CT, but the result at quantitative evaluation showed a change of less than 5% in all experimental conditions, maintaining quantitative accuracy(RC less than 0.05) without much influence.

• Journal of Ginseng Research
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• v.10 no.2
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• pp.200-208
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• 1986

It was attempted in this study to investigate the effect of ginseng saponin on several glycolytic enzymes of yeast cell and the following results were obtained. The amount of $CO_2$formed during the incubation of yeast cells in medium containing saponin fraction of Panax ginseng C.A. Meyer was greater than that of control cells and found that the $CO_2$ formation was greatest when the cells were grown in the medium containing 10$^{-3}$% of the saponin fraction, at which the uptake of inorganic phosphate and glucose consumption were also increased. Radioactivity study of several glycolytic intermediates of yeast cells cultured in the medium containing [U-$^{14}$C]-glucose showed that the radioactivity of fructose 6-phosphate of test cells was as much as 1.6times that of control group. On the other hand, the radioactivity of pyruvate of test cells was considerably decreased compared to control. Investigation of the effect of ginseng saponin on yeast hexokinase, phosphoglucose isomers, pyruvate kinase and perverted decarboxylase in vitro showed that the maximum activities of the above enzymes were observed when the concentration of ginseng saponin was 10-$^{-5}$% in the reaction mixture. It seemed that the ginseng saponin stimulated both glycolytic enzymes such as hexokinase, phosphoglucose isomers and perverted decarboxylase significantly.