• Journal of the Korean Society of Radiology
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• v.16 no.3
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• pp.357-363
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• 2022

This study aims to improve the safety inspection awareness of occupational exposure and help radiation safety management by analyzing radiation exposure doses by occupational type of radiation related-workers and radiation workers. Radiation-related workers and radiation workers were classified into three occupations (radiological technologist, doctors, and nurses). A nominal risk coefficient based on ICRP 103 was used to calculate the probability of causing side effects of the lungs due to exposure doses. As a result of analyzing the exposure dose of all workers for one year, the exposure dose of radiological technologist among radiation-related workers was 1.63 ± 2.84 mSv, doctors 0.12 ± 0.22 mSv, and nurses 0.59 ± 1.08 mSv. The one-year deep dose for radiation workers was 2.44 ± 3.30 mSv for radiological technologists, 0.19 ± 0.26 mSv for doctors, and 0.12 ± 0.00 mSv for nurses. Due to this dose, the probability of causing side effects in the lungs was 1.2 per 100,000 radiological technologist, 0.096 doctors, and 0.06 nurses. In this study, it is believed that the probability of side effects on lungs by occupation of radiation exposure dose will be studied and used as useful data for radiation safety management in relation to probabilistic effects in the future.

• Nuclear Engineering and Technology
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• v.53 no.1
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• pp.273-281
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• 2021

The radiological safety of the spent resin treatment facility with a¹⁴C treatment capacity of 1 ton/day was evaluated in terms of the external and internal exposure of worker according to operation scenario. In terms of external dose, the annual dose for close work for 1 h/day at a distance of more than 1 m (19.8 mSv) satisfied the annual dose limit. For 8 h of close work per day, the annual dose exceeded the dose limit. For remote work of 2000 h/year, the annual dose was 14.4 mSv. Lead shielding was considered to reduce exposure dose, and the highest annual dose during close work for 1 h/day corresponded to 6.75 mSv. For close work of 2000 h/year and lead thickness exceeding 1.5 cm, the highest value of annual dose was derived as 13.2 mSv. In terms of internal exposure, the initial year dose was estimated to be 1.14E+03 mSv when conservatively 100% of the nuclides were assumed to leak. The allowable outflow rate was derived as 7.77E-02% and 2.00E-01% for the average limit of 20 mSv and the maximum limit of 50 mSv, respectively, where the annual replacement of the worker was required for 50 mSv.

• Biomolecules & Therapeutics
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• v.19 no.2
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• pp.248-254
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• 2011

Biotransformation of pharmacologically inactive lactone prodrug simvastatin (SV) into pharmacologically active simvastatin ${\beta}$-hydroxy acid (SVA) exhibits inter-species differences due to variations in amount and activity of esterase enzymes. In this study, we investigated the pharmacokinetics (PK) of SV and its metabolite SVA following oral doses of SV from controlled-release (CR) tablets and immediate-release (IR) tablets in rodent and canine animal models that features different esterase activity. In rat PK study, no SV was detected in plasma for both formulations due to rapid hydrolysis of SV into SVA by plasma esterase. Besides, no significant differences in PK parameters of SV or SVA were observed between both species. In dog PK study, the relative oral bioavailability of CR tablets in terms of SV was 72.3% compared to IR tablets. Regarding formulation differences in dogs, CR tablets exhibited significantly lower $C_{max}$ (p<0.05), and higher $T_{max}$ (p<0.01) and MRT (p<0.01) for both SV and SVA compared to IR tablets. Accordingly, CR tablets of SV with prolonged drug release profiles in both species might be a potential candidate for a more effective delivery of SV with reduced side effects. Besides, similar PK parameters of SV and SVA in both species despite variation in enzyme activities suggested involvement of equally potent biotransformation pathways in these animal species.

• Korean Journal of Radiology
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• v.21 no.1
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• pp.68-76
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• 2020

Objective: To survey care providers' willingness to use 2-mSv computed tomography (CT) in their usual practice for adolescents and young adults with suspected appendicitis. Materials and Methods: An ethical committee approved this prospective study. We introduced 2-mSv CT in 20 hospitals through a pragmatic clinical trial. At the final phase of the trial, we invited 698 potentially-involved care providers in the survey regarding their willingness to use 2-mSv CT. Multivariable logistic regression analyses were performed to identify factors associated with willingness. Nine months after the completion of the trial patient recruitment, we surveyed whether the hospitals were using 2-mSv CT in usual practice. Results: The analyses included responses from 579 participants (203 attendings and 376 trainees; 221 radiologists, 196 emergency physicians, and 162 surgeons). Regarding the willingness to immediately change their standard practice to 2-mSv CT, 158 (27.3%), 375 (64.8%), and 46 (7.9%) participants responded as "yes" (consistently), "partly" (selectively), and "no", respectively. Willingness varied considerably across the hospitals, but only slightly across the participants' departments or job titles. Willingness was significantly associated with attendings (p = 0.004), intention to maintain the dedicated appendiceal CT protocol (p < 0.001), belief in compelling evidence on the carcinogenic risk of conventional-dose CT radiation (p = 0.028), and hospitals having more than 1000 beds (p = 0.031). Fourteen of the 20 hospitals kept using 2-mSv appendiceal CT in usual practice after the trial. Conclusion: Despite the extensive efforts over the years of this clinical trial, many care providers were willing to use 2-mSv CT selectively or not willing to use.

• Journal of Korean Academy of Oral and Maxillofacial Radiology
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• v.25 no.1
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• pp.27-38
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• 1995

The organ or tissue doses were determined with head and neck phantom measurement for multiple axial scans (36 slices), multiple coronal scans (13 slices), 3 types of single axial scans(orbit, maxillary sinus and mandibular canal) and single coronal scan (maxillary sinus). For each scan sequence 30 TLDs were placed in selected sites(16 internal sites and 14 external sites) in a tissue-equivalent phantom. The exposure was made at 120kVp, 500mAs with 5 mm slice width. The results were as follows : 1. In multiple axial scans, the greatest effective dose recorded was that delivered to the thyroid glands(2.77 mSv) and the least was that received by the skin(0.05 mSv). From these data, stochastic effects were 202.2x10/sup -6/ and 3.7×10/sup -6/, respectively. 2. In multiple coronal scans, the greatest effective dose recorded was that delivered to the salivary glands(0.58 mSv) and the least was that received by the skin(0.01 mSv). From these data, stochastic effects were 42.2×10/sup -6/ and 0.7×10/sup -6/, repectively. 3. Among single axial scans, the greatest effective dose recorded was that delivered to the salivary gland(0.38 mSv) in maxillary sinus scan. From this data, stochastic effect was 27.7×10/sup -6/. 4. In single coronal scan, the greatest effective dose recorded was that delivered to the salivary gland(0.01 mSv). From this data, stochastic effect was 1.0×10/sup -6/. 5. The equivalent dose measured that delivered to the lens of the eyes was 69.64 mSv in multiple axial scan, 39.32 mSv in multiple coronal scan and 36.77 mSv in single axial scan(orbit).

• Journal of the Korean Society of Radiology
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• v.13 no.2
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• pp.271-281
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• 2019

This study investigated the shielding efficiency of various types of shielding materials and measured the dose by organ using the phantom. Results of Shielding Efficiency Measurement Using Personal Radiation Meter. Among the various shielding materials, 1.1 mm RNS-TX composed of nano tungsten showed the highest shielding efficiency and 0.2 mm lead shielding showed the lowest shielding efficiency. 99mTc 30 mCi was exposed to the phantom for 120 minutes and the result of the measurement of the organs. 20.53 mSv without radiation protective clothing, 8.75 mSv when wearing 0.25 mm Pb protective clothing, 6.03 mSv when wearing 0.5 mm Pb protective clothing. 131I 2 mCi mCi was exposed to the phantom for 120 minutes and the result of the measurement of the organs. 7.71 mSv without radiation protective clothing, 4.88 mSv when wearing 0.25 mm Pb protective clothing, 2.79 mSv when wearing 0.5 mm Pb protective clothing. 18F 5 mCi was exposed to the phantom for 120 minutes and the result of the measurement of the organs. 16.39 mSv without radiation protective clothing, 15.84 mSv when wearing 0.25 mm Pb protective clothing, 12.52 mSv when wearing 0.5 mm Pb protective clothing. None of the radiation workers working in the nuclear medicine department exceeded the dose limit. However, when compared with other workers in the hospital, they showed a relatively high dose. Therefore, it is necessary to prepare measures to reduce and manage the dose of radiation workers in the nuclear medicine department through the wearing of radiation protective clothing made of lightweight, shielding material with good shielding efficiency, circulation task, task sharing, and substitution equipment such as auto dispenser.

• The Korea Journal of Herbology
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• v.34 no.1
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• pp.109-116
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• 2019

Objectives : This study aimed to analyze contents of chlorogenic acid among major ingredients and determine the optimal solvent for the antioxidant activity from Solidago virga-aurea var. gigantea(SV) aerial part. Methods : Mature aerial part of extracted SV at the first crop on June 2018 was used. SV was mixed with each at the ethanol concentrate rates of water, 10, 30, 50, 70, and 100% and extracted them for three times for eight hours at $70^{\circ}C$. The contents of chlorogenic acid and seven kinds of antioxidant activities were measured in SV extracts. Results : The highest the contents of chlorogenic acid was from 10% ethanol extracts showed. Total polyphenol and flavonoids of SV extracts were 126.16 mg/g and 105.84 mg/g, respectively. Scavenging activities of DPPH, ABTS, and hydroxyl radical significantly increased in a dose-dependent in SV extracts, while it was almost similar with control at the concentration of $500{\mu}g/mL$. $Fe^{2+}$ chelating activity significantly increase in a dose-dependent in SV extract, it was lower than control. Nitrite scavenging activity increased, dose-dependent in the sequence of pH 1.2> pH 3.0 > pH 6.0 in SV extracts, while it was almost similar with control at the concentration of $500{\mu}g/mL$, pH 1.2, and pH 3.0. Conclusions : Thus, this study found that higher contents of chlorogenic acid and excellent antioxidant activity were contained in 10% ethanol extracts in mature aerial part of SV. It is expected to be used as basic data as natural antioxidant materials.

• Journal of the Korean Society of Radiology
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• v.12 no.7
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• pp.807-812
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• 2018

In this study, we investigated the conditions used in setting the recommendation level of general radiography diagnostic reference and tried to evaluate the effective dose and biological evaluation using PCXMC v2.0 program. As a result based on the effective dose of male in ICRP 60, the highest Pelvis AP was 0.794 mSv. The lowest Chest PA was 0.050 mSv. In the case of ICRP 103, the highest T-Spine AP was 0.906 mSv The lowest Chest PA was 0.052 mSv. For 40 years old male and female adults, effective doses of general radiography were evaluated and even if the medical exposures are not subject to the limit of dose, efforts should be made to reduce the medical exposures of the people by keeping the dose below the recommended amount in order to minimize the probable effect of radiation hazard.

• Journal of Radiation Protection and Research
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• v.15 no.2
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• pp.87-100
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• 1990

For the quantitative evaluation and assessment of radiation exposure from terrestrial component of natural environmental radiation, successive thermoluminescence dosimetry and periodical in-situ gamma ray spectrometry were carried out for a period of 24 months. LiF PTFE dise TLDs and $3&{\phi}{\times}3'$cylindrical NaI(Tl)scintill ation detector in association of portable multichannel analyzer (4096 ch) were used in this study. The doses measured were evaluated and assessed in terms of effective dose equivalent. As a concomitant output, the dose equivalent due to ionizing component of cosmic ray was able to be evaluated. According to the results obtained in terms of variance weighted mean, the annual effective dose equivalents of terrestrial gamma ray and cosmic ray ionizing component in Taejeon area came out to be $564{\pm}4\;{\mu}Sv(64.8{\pm}0.5nSv{\cdot}h^{-1}$ and $300{\pm}2\;{\mu}Sv(34.3{\pm}0.2nSv{\cdot}h^{-1}$, respectively, which are reasonable comparably with that appeared in UNSCEAR Report[28]as per caput annual effective dose equivalent in 'areas of normal background radiation'.

• Journal of radiological science and technology
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• v.37 no.3
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• pp.233-238
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• 2014

The amount of environmental radiation was measured in the indoor(basement) and outdoor(rooftop) of the two buildings of the University (the old building and the new building) in Suwon City, Gyeonggi Province. Measuring the environmental radiation dose from the first week of April 2013 to last week of March 2014, Twice a week, one year. The measured results were as follows. 1. The average annual environmental radiation of the two buildings were $0.169727{\mu}Sv/hr$. The lowest value was $0.0760{\mu}Sv/hr$ whereas the highest value was $0.3000{\mu}Sv/hr$. 2. The amount of environmental radiation dose was $0.176373999{\mu}Sv/hr$ in the old building and the amount of environmental radiation dose was $0.163052885{\mu}Sv/hr$ in the new building. The old building environmental radiation dose was higher then the new building. 3. The month of the lowest amount of environmental radiation dose in a year was November resulting in $0.152844{\mu}Sv/hr$ whereas May was found the month of the highest amount of environmental radiation dose showing with $0.197222{\mu}Sv/hr$. 4. The amount of environmental radiation dose in the indoor(basement) was $0.164649{\mu}Sv/hr$ and the amount of environmental radiation dose of the outdoor(rooftop) was $0.174779{\mu}Sv/hr$. And the outdoor(rooftop) was higher than the indoor(basement). 5. Depending on seasonal, the lowest amount of environmental radiation dose was in winter with $0.1632{\mu}Sv/hr$ while spring was the season with the highest amount of environmental radiation dose with $0.183846{\mu}Sv/hr$. The measured amount was high in the order of spring, summer, autumn, and winter.