• Journal of radiological science and technology
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• v.21 no.2
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• pp.26-30
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• 1998

We tried to study in order to furnish the data for medical exposure dose and scattered ray in radiography. As the tables(from 1 to 3) show, we can presume, by means of a concrete numerical value, the amount of results affected by patient radiation exposure dose and somatic effect in radiography. However, there are many difficulties in the difference of exposure factor in each hospital, the accuracy of measuring by tracebility, shortage of exposure dose data especially in the area of children, and portable radiography, etc. In the radiation examination, it is considered if the gained benefit to the patient due to radiation is more than the risk of radiation, then the medical exposure is thought to be justified. Therefore, the radiotechnologists should continually make an effort to develop and study new techniques so as to reduce patient exposure dose.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.21 no.2
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• pp.183-191
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• 2023

The potential impact of hypothetical accidents that occur during the immediate and deferred dismantling of the Kori Unit 1 steam generator has been comprehensively evaluated. The evaluation includes determining the inventory of radionuclides in the Steam Generator based on surface contamination measurements, assuming a rate of release for each accident scenario, and applying external and internal exposure dose coefficients to assess the effects of radionuclides on human health. The evaluation also includes calculating the atmospheric dispersion factor using the PAVAN code and analyzing three years of meteorological data from Kori NPP to determine the degree of diffusion of radionuclides in the atmosphere. Overall, the effective dose for residents living in the Exclusion Area Boundary (EAB) of Kori NPP is predicted, an it is found that the maximum level of the dose is 0.034% compared to the annual dose limit of 1 mSv for the general public. This implies that the potential impact of hypothetical accidents on human health discussed above is within acceptable limits.

• Nuclear Engineering and Technology
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• v.56 no.7
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• pp.2781-2789
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• 2024

We developed lead gloves that minimize radiation dose to the operator's hands during interventional radiological procedures and that do not impede the operator's surgical capabilities. Existing lead gloves can protect the operator's hands by shielding radiation, but use of such gloves may impair preception sensitivity, resulting in a reduction in the operator's surgical ability. Accordingly, in this study, we developed modified lead gloves that can reduce radiation dose while maintaining operator sensitivity during procedures by modifying the operator's main surgical finger area in existing lead gloves. To evaluate the performance of developed modified lead gloves, radiation was applied in surgical conditions without gloves and with surgical gloves, lead gloves, and modified lead gloves. The radiation dose was evaluated for each condition. When the modified lead gloves were worn, the degree of shielding was similar to when conventional lead gloves were worn. Based on these results, if the operator wears modified lead gloves during interventional radiological procedures, they will protect the hands from radiation while maintaining physical sensitivity in the hands.

• Journal of radiological science and technology
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• v.44 no.3
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• pp.195-203
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• 2021

Although intra oral dental x-ray is a lower dose than other radiological examinations, pediatric patients are known to have a higher risk of radiation damage than adults. For this reason, pediatric dental x-ray requires management of dose evaluation and imaging conditions during the examination. In this study, the dose calculation program ALARA-Dental(child/adult) was used to evaluate the organ dose and effective dose exposed to each examination site during intra oral imaging of children during dental radiographic examination, and dose analysis according to the imaging conditions was performed. As a result, the highest organ dose distribution was shown at 0.044 ~ 0.097 mGy in all are as of the mucous membrane of oral cavity except for the maxillary incisors and canines. Also, in the case of the thyroid gland, the maxillary canine and maxillary premolar examination showed 0.027 and 0.020 mGy, respectively, and the dose distribution was 15.4% to 70.0% higher than that of the mandibular examination. As for the effective dose calculated during intra oral imaging, the maxillary anterior and canine examinations showed the highest effective doses of 0.005 and 0.004 mSv, respectively, and the maxillary area examination showed a higher dose distribution on average than the mandible.

• Journal of radiological science and technology
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• v.46 no.2
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• pp.123-129
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• 2023

Interventional cardiology procedures can involve relatively high radiation doses compared to conventional radiography. During CAG, CAG + PCI and PCI the same area is exposed to radiation for a long period. In this study, radiation exposure data of 421 examinations in Gyeongsang area were collected, and the DRLs and ADs in actual medical practice for three types of interventional cardiology procedures in Korea were established. In CAG 286 case, 75th percentile DRLs and ADs of the total DAP were 55.89 Gy·cm² and 37.47 Gy·cm² , respectively. In CAG + PCI 92 case, those values were 222.84 Gy·cm² and 117.51 Gy·cm² respectively. In PCI 43 case, those values were 198.73 Gy·cm² and 120.13 Gy·cm² respectively. In this study, for the first time, the diagnostic reference level of interventional cardiology procedures in Gyeongsang area were established. Using the diagnostic reference level of interventional cardiology procedures derived from this study, it will help to identify and improve the level of exposure dose in the region and country.

• Progress in Medical Physics
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• v.22 no.2
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• pp.61-66
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• 2011

In this study, we evaluated the effect of grid size on dose calculation accuracy using 2 head & neck and 2 prostate IMRT cases and based on this study's findings, we also evaluated the efficiency of a 2D diode array detector for IMRT quality assurance. Dose distributions of four IMRT plan data were calculated at four calculation grid sizes (1.25, 2.5, 5, and 10 mm) and the calculated dose distributions were compared with measured dose distributions using 2D diode array detector. Although there was no obvious difference in pass rate of gamma analysis with 3 mm/3% acceptance criteria for the others except 10 mm grid size, we found that the pass rates of 2.5, 5 and 10 mm grid size were decreased 5%, 20% and 31.53% respectively according to the application of the fine acceptance criteria, 3 mm/3%, 2 mm/2% and 1 mm/1%. The calculation time were about 11.5 min, 4.77 min, 2.95 min, and 11.5 min at 1.25, 2.5, 5, and 10 mm, respectively and as the grid size increased to double, the calculation time decreased about one-half. The grid size effect was observed more clearly in the high gradient area than the low gradient area. In conclusion, 2.5 mm grid size is considered acceptable for most IMRT plans but at least in the high gradient area, 1.25 mm grid size is required to accurately predict the dose distribution. These results are exactly same as the precious studies' results and theory. So we confirmed that 2D array diode detector was suitable for the IMRT QA.

• Journal of radiological science and technology
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• v.42 no.3
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• pp.209-215
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• 2019

Comparison of the effective dose of the chest and the equivalent dose of the lens site in the radiation workers working at four medical institutions with the PET / CT room located in one metropolitan city and province from April 1 to June 30, 2018 Respectively. Radioactive medicine were measured at the time of dispensing and at the time of injection. In this experiment, the average dispensing time per patient was 5.7 minutes and the average injection time was 3.1 minutes. The equivalent dose at the lens site was $0.78{\mu}Sv/h$ for 1 mCi, and the effective dose for chest was $0.18{\mu}Sv/h$ per 1 mCi. The equivalent dose at the lens site during injection was $0.88{\mu}Sv/h$ per mCi and the effective dose of chest was $0.20{\mu}Sv/h$ per mCi. The daily effective dose of the chest was $0.9{\pm}0.6{\mu}Sv$ and the equivalent dose of the lens site was $3.6{\pm}1.4{\mu}Sv$ during daily dosing for 20 days. The effective dose of the chest during the day was $0.6{\pm}0.5{\mu}Sv$ and the equivalent dose of the lens was $2.2{\pm}1.0{\mu}Sv$. At the time of dispensing, the equivalent dose of the lens was $0.187{\pm}0.035mSv$, the effective dose of the chest was $0.137{\pm}0.055mSv$, the equivalent dose of the lens was $0.247{\pm}0.057mSv$, and the effective dose of the monthly chest was $0.187{\pm}0.021mSv$. As a result of the corresponding sample test, the equivalent dose and the effective dose of the chest, the effective dose of the chest, the effective dose of the chest, the effective dose of the chest, The equivalent dose of the lens and the effective dose of the chest were statistically significant (p<0.05) with a significance of 0.000. However, there was no statistically significant difference (p>0.05) between the equivalent dose and the effective dose of the chest, the equivalent dose of the lens at the time of injection, and the effective dose of the chest at 0.138 and 0.230, respectively.

• The Korean Journal of Applied Statistics
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• v.33 no.2
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• pp.137-145
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• 2020

Phase I clinical trials (Dose Finding Studies) are the first step in administering new drugs developed through animal experiments or in vitro experiments to humans. An important area of interest in designing Phase I clinical trials is determining the dose that provides the greatest efficacy and acceptable safe dose to the patient. In this paper, we propose a method to determine the maximum tolerated dose considering efficacy and safety using Biased coin design and stopping rule. The proposed method is compared with existing methods through simulation.

• Korean Journal of Digital Imaging in Medicine
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• v.13 no.4
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• pp.153-156
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• 2011

This study, which is proceeded in the department of nuclear medicine, aims at preventing unnecessary radiation exposure to the patients and the people near the patients by understanding and presenting the realities about the isolating period for the high dose radioiodine patients after total thyroidectomy in the 7 general hospitals in metropolitan area. Theoretically, the physical half-life of the high dose radioiodine is 8 days. Radioiodine lower than 100 mCi usually is eliminated all in 2 days 1 night considering the biological half-life and the amount of excreting radioiodine The hospitalization standard of the patients treated with high-dose radioiodine therapy has been established according to the fact above. Investigation of the data and questionnaire from the hospital have proven that some hospitals didn't even measure the acceptable dose because of the faith in the vague data. Besides, the some of those inevitably let the readmitting patients exceeding the acceptable dose be in the general ward, not in the isolation ward, because the number of the isolation rooms is relatively smaller than the patients. Thus, we want to contribute that patients understand the realities and the hospitals consider the relevant problem actively so that the problem will be settled by this journal.

• The Journal of Engineering Geology
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• v.29 no.4
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• pp.461-468
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• 2019

Gamma-radiation dose rates were measured at 77 points around the Ogcheon lower phyllite zone (og2) in Goesan County, Korea, using gamma-ray spectrometry. Sample K contents were in the range 1.8-8.8% (average 4.6%), highest in Kgr. The eU contents were 0.2-217.9 ppm (average 16.7 ppm), highest in og2 (median 29.6 ppm). The eTh contents were 11.9-76.5 ppm (average 29.5 ppm) and the average eTh content of Kgr was 45.4 ppm, higher than those of Ogcheon meta-sedimentary rocks (og1, og2, and og3) (26.6-30.6 ppm). Except for some high-uranium sites in og2, ⁴⁰K is the main radioactive material contributing to the gamma-radiation dose in the study area. Our results indicate that the outdoor effective dose rate of the area is 0.08-1.71 mSv y^-1 (average 0.28 mSv y^-1), with most areas apart from three points in og2 displaying dose rates <1 mSv y^-1, which is the normal natural radiation background level.