• Korean Journal of Environmental Agriculture
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• v.26 no.2
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• pp.186-191
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• 2007

The objective of this research was to assess the reliability of data and to improve nuclear analytical techniques concerning the Domestic Radioactivity Intercomparison program for environmental radioactivity monitoring of Jeju from 1998 to 2006. Gross beta for filter papers and water samples was determined, and gamma nuclides for natural and artificial nuclides in soil and water samples were analyzed. The gross beta activity of all samples except for the water samples of 1998 and 1999 showed a good agreement within the confidence intervals. In gamma nuclides, $^{40}K$ and $^{137}Cs$ of soil samples and most nuclides in the water samples, with the exception of several nuclides, were evaluated to be reliable. Based on these results, it is considered that a reliable method for the analysis and monitoring of environmental radioactivity were established, which may play an important role in case of emergency radiation accident.

• Journal of Korean Academy of Oral and Maxillofacial Radiology
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• v.20 no.1
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• pp.53-62
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• 1990

This experiment was performed to clarify the effects of /sup 60/Co gamma irradiation on secretory function, amylase activity and contents of nucleic acids of parotid gland in rat. Experimental animals were divided into 6th hours, 3rd, 7th, 14th and 28th days after irradiation and control. The experimental animals are singly irradiated with 20Gy (2,000rad) through protective lead block. Secretory function of parotid gland was evaluted by uptake and clearance of /sup 99m/TcO₄. /sup 99m/TcO₄. 0.2μ ci/gm, was injected into peritonium in uptake groups. Rats were sacrified with cervical dislocation after 30 minutes and gland was excised. In the clearance group. pilocarpine nitrate (8㎎/㎏) was intraperitoneally injected at 30 minutes after /sup 99m/TcO₄ injection and rats were sacrified 30 minutes after pilocarpine injection. Radioactivity of excised parotid gland was measured by using of gamma counter and stimulation-secretion coefficients, uptake radioactivity divided by clearance radioactivity, was calculated. Amylase activity and contents of DNA and RNA were determined by spectrophotometry. The results obtained were as follows: 1. In the uptake test, the radioactivity of /sup 99m/TcO₄ per unit weight increase in experimental group except 6th hours group, compared with control groups and showed a peak at 3rd days after irradiation. 2. In the clearance test, the radioactivity of /sup 99m/cO₄per unit weight rose to a peak at 3rd days after irradiation and gradually recovered thereafter. 3. Stimulation-secretion coefficient of parotid gland decreased at 6th hours, 3rd and 7th days after irradiation, and gradually increased. 4. Amylase activity of parotid gland decreased in 3rd and 7th days group, and especially lowest in 3rd days after irradiation. 5. The contents of DNA showed no definite difference in all the experimental groups, but RNA was seemed to decrease with time after irradiation.

• The Korean Journal of Nuclear Medicine
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• v.16 no.1
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• pp.55-61
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• 1982

Biodistribution studies has been carried out to elucidate the cause of poor bone imagings often encountered in using $methylenediphosphonate(MDP)-^{99m}Tc$ and to establish effective conditions in using the popular bone imaging agent. After 150 minutes from the I.V. injection of $MDP-^{99m}Tc$ to mice, the radioactivities accumulated at bone(B), liver(L), and stomach(S) were counted. The radiochemical purity (RCP), the volume, the radioactivity concentration and the amount of radioactivity of $MDP-^{99m}Tc$ were controlled. Data were expressed either in %cpm/g organ or % cpm/organ. The organ distribution ratios(B/L and B/S) were correlated with the RCP, the volume of injection, the radioactivity concentration etc. Results indicated that the RCP plays a major role in biodistributions. High radioactivity concentration and injection of a small amount is recommended. Negligible effect was observed with the amount of radioactivity. It has been confirmed that the up-to-date methods of RCP determinations cannot sensitively detect the sharply affecting trace impurities. A particular biodistribution pattern of crossed B/L and B/S lines was observed in case of using $MDP-^{99m}Tc$ of low RCP. In such a case, rather a higher dosage would be effective for improving the contrast between bone and liver.

• Journal of the Korean Society of Radiology
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• v.15 no.4
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• pp.533-538
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• 2021

^99mTcO₄^- is used to measure thyroid uptake. When measuring background radioactivity of the thigh, the distance between the detector and the thigh was 20 cm at a position 10 cm above the knee from the knee to the pelvis. At 25 cm, many hospitals are measuring at different distances. The purpose of this study was to study the difference in effectiveness in obtaining the thyroid uptake rate by quantitatively analyzing the uptake rate measurement at two distances. As a result, the average thyroid uptake rate measured at 20 cm in the thigh of 50 patients was 3.532±4.312%, and the average thyroid uptake rate measured at 25 cm was 3.680±4.304%. As a result of the thyroid uptake rate test result, the femoral background radioactivity value measured at a distance of 20 cm was relatively higher than the background radioactivity value measured at a distance of 25 cm, and as a result, the thyroid uptake rate was 0.148% lower.

• 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.

• Archives of Pharmacal Research
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• v.9 no.3
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• pp.157-161
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• 1986

Isolated calf thymus nuclei were in vitro methylated with S- adenosy-L-methyl-$^{14}C$ methionine, and the proteins were fractionated according to their solubilities. Histone fraction ($H_{2}SO_{4}$-soluble fraction) contained approximately 60% total radioactivity incorporated, while "residual protein" which was ($H_{2}SO_{4}$-insoluble contained the remaining radio-activity. The "residual protein" was further fractionated into various acidic proteins, which contained very littel of the radioactivity. However, the protein fraction eluted from DEAE-cellulose with 0.5 N NaOH contained the largest amount of radioactivity. This protein was found to be basic in nature by amino analysis.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.24-31
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• 2004

In order to decommission safely nuclear power plant, it is necessary for the procedure of residual radioactivity investigation in site to provide detailed guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with a dose or risk-based regulation. This study presents the procedure of residual radioactivity investigation in decommissioning site - Historical Site Assessment, Scoping Survey, characterization Survey, Remedial Action Support Survey, Final Status Survey - on the basis of MARSSIM(Multi-Agency Radiation Survey and Site Investigation Manual) and investigation cases of decommissioned or decommissioning nuclear power plant.

• Journal of Ginseng Research
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• v.7 no.2
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• pp.108-114
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• 1983

1. To know the site of saponin synthesis in this plant, 4-years old Panax ginseng C.A. Meyer was administered with 1, 2-l4C-acetate (Na salt, 10 ucilplant) by stem injection and was continued to grow for 3 weeks and the distribution of the radioactivity in leaf, stem and root part was identified. The percentage of radioactivity recovered was about 3.99%. 2. The sliced roots or leaf discs (2g) were bathed in the reaction mixture containing sugar, ATP, NADPH, and the distribution of the radioactivity of the fractions (sugar, saponin, sapogenin) was identified. 3. It seemed that major synthesized saponins in roots and leaves are dial and triol-type, respectively. Although both types of saponins are synthesized in roots, the main saponins seemed to be dial saponins and a significant portion of triol saponins are supplied from leaves through stem.

• Journal of Radiation Industry
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• v.10 no.1
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• pp.37-41
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• 2016

The recent prevalence of PET examinations in Korea has led to an increase in the number of cyclotrons. The medical isotope $^{18}F$ produced in most cyclotron facilities currently operating in Korea is emitted into the environment during the production of [$^{18}F$]FDG, a cancerdiagnosis reagent. The amount of [$^{18}F$]FDG synthesized determines the radioactive concentration of $^{18}F$ in the exhaust. At some facilities, this amount temporarily exceeds the emission limit. In this study, we evaluated the $^{18}F$ radioactivity concentration in the exhaust from the cyclotron facility at Chosun University. The $^{18}F$ radioactivity concentration was measured using an air sampler and a HPGe semiconductor detector. The measurements showed that the radioactive concentration of $^{18}F$ in the exhaust at the cyclotron facility at Chosun University was the highest during [$^{18}F$]FDG synthesis but remained under the legal limit of $2,000Bq\;m^{-3}$.

• The Korean Journal of Nuclear Medicine
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• v.28 no.3
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• pp.357-363
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• 1994

We evaluated the diagnostic accuracy of $^{99m}Tc$-DISIDA scintigrauhy as a mean of differentiating biliary atresia from neonatal hepatitis. $^{99m}Tc$-DISIDA scintigraphy was visually interpreted by assessing the presence or absence of radioactivity in the intestine or gall bladder. In patients without intestinal radioactivity, we measured the hepatic retention index and the hepatic uptake index. The hepatic retention Index was expressed as the amount of change of liver activity from 5 minutes to 30 minutes postinjection. The hepatic uptake Index was graded visually with 5 minute images using the following scoring scheme : grade 0(normal hepatic uptake), grade 1(decreased hepatic uptake), grade 2(hepatic uptake equal to cardiac uptake), and grade 3(hepatic uptake less than cardiac uptake). Age, total bilirubin, and hepatic uptake index were compared between the biliary atresia and the neonatal hepatitis group, between neonatal hepatitis patients with and without intestinal radioactivity, and between the biliary atresia and neonatal hepatitis patients with absent intestinal radioactivity. The results were as follows ; 1) None of the 30 biliary atresia patients showed intestinal radioactivity, while 31/40 neonatal hepatitis patients showed intestinal radioactivity. The sensitivity, specificity, and accuracy of the presence of intestinal radioactivity ?or the diagnosis of biliary atresia was 100%, 78%, and 87%, respectively. 2) In patients with absent intestinal radioactivity the mean hepatic retention index was $1.5{\pm}0.6$ in the 16 biliary atresia patients, and $1.1{\pm}0.2$ in the 7 neonatal hepatitis patients(p<0.01). All 7 patients with hepatic retention index over 1.5 had biliary atresia. But there were 9 patients with biliary atresia below 1.5. 3) No significant differences were found in age, total bilirubin, or hepatic uptake Index between biliary atresia and neonatal hepatitis patients. However there were differences in age, total bilirubin, and hepatic uptake index between neonatal hepatitis patients with and without intestinal radioactivity. The hepatic uptake index was significantly lower, age was old, and total bilirubin was low in the group with intestinal radioactivity compared the group without intestinal radioactivity(p<0.05). Relation between total bilirubin and the hepatic uptake index was that total bilirubin was relatively low at normal hepatic uptake index in biliary atresia and neonatal hepatitis patients. 4) When hepatic uptake index and hepatic retention index were high it suggest that biliary atresia is more likely, considered relation between hepatic uptake Index and the hepatic retention index. Thus, we conclude that $^{99m}Tc$-DISIDA scintigraphy is accurate in the differential diagnosis of biliary atresia and neonatal hepatitis. In patients without intestinal radioactivity, the hepatic retention index and hepatic uptake index, along with the patient's age and total bilirubin level may supplement diagnosis and improve diagnostic accuracy.