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.
Cotton has no adsorption ability for the cationic dye and heavy metal but, if anionized cotton can be made, it will be possible. In this study, to enable the anionisation of cotton fabric, it was modified using sodium vinylsolfonate(SV) as the anionisation reagent, employing a pad-dry-cure(PDC) technique. The effects of curing time, treatment concentrations of urea, sodium hydroxide and SV on the weight increase were experimented and then, the physical characterizations of sulfoethyl cotton(SEC) depending on the finishing conditions were estimated, thus the application possibility of SV as anionisation reagent was investigated. It was not much changed by anionisation except wrinkle recovery. And the structure of SEC was elucidated by Raman and NMR spectoscopy. The feasibility of using Raman and NMR spectroscopy with the band at $1,043cm^{-1}$, and 50.5ppm, respectively as marker band to determine sulfoethyl group of SEC was reported. The total degree of SV substitution(DSV) was determined via elemental analysis. SEC with diverse total DSV up to 0.066 was obtained. In the thermal decomposition(pyrolysis) by DSC, it can be found that the pyrolysis temperature was about $30^{\circ}C$ lower than that of non-treated cotton fabric.
The frequency of diagnostic radiation examinations in medical institutions has recently increased to 220 million cases in 2011, and the annual exposure dose per capita was 1.4 mSv, 51% and 35% respectively, compared to those in 2007. The number of chest radiography was found to be 27.59% of them, the highest frequency of normal radiography. In this study, we developed a shielding device to minimize radiation exposure by shielding areas of the body which are unnecessary for image interpretation, during the chest radiography. And in order to verify its usefulness, we also measured the difference in entrance surface dose (ESD) and the absorbed dose, before and after using the device, by using an international standard pediatric (10 years) phantom and a glass dosimeter. In addition, we calculated the effective dose by using a Monte Carlo simulation-based program (PCXMC 2.0.1) and evaluated the reduction ratio indirectly by comparing lifetime attributable risk of cancer incidence (LAR). When using the protective device, the ESD decreased by 86.36% on average, nasal cavity $0.55{\mu}Sv$ (74.06%), thyroid $1.43{\mu}Sv$ (95.15%), oesophagus $6.35{\mu}Sv$ (78.42%) respectively, and the depth dose decreased by 72.30% on average, the cervical spine(upper spine) $1.23{\mu}Sv$ (89.73%), salivary gland $0.5{\mu}Sv$ (92.31%), oesophagus $3.85{\mu}Sv$ (59.39%), thyroid $2.02{\mu}Sv$ (73.53%), thoracic vertebrae(middle spine) $5.68{\mu}Sv$ (54.01%) respectively, so that we could verify the usefulness of the shielding mechanism. In addition, the effective dose decreased by 11.76% from $8.33{\mu}Sv$ to $7.35{\mu}Sv$ before and after wearing the device, and in LAR assessment, we found that thyroid cancer decreased to male 0.14 people (95.12%) and female 0.77 people (95.16%) per one million 10-year old children, and general cancers decreased to male 0.14 people (11.70%) and female 0.25 people (11.70%). Although diagnostic radiation examinations are necessary for healthcare such as the treatment of diseases, based on the ALARA concept, we should strive to optimize medical radiation by using this shielding device actively in the areas of the body unnecessary for the diagnosis.
This study investigated the radiation protection of therapeutic radiologists. Based on the change in X-ray energy and MU value, the space dose rate in the treatment room after the irradiation was measured. 6MV, 10MV and 15MV photon beams were exposed to radiation inside the treatment room based on 300MU, 600MU and 1000MU using a linear accelerator. And repeated 10 times under the same conditions. As a result of the experiment, 0.1555 μSv/h for 6MV 300MU, 0.157 μSv /h for 300sec, 0.152 μSv/h, 0.156 μSv/h for 600MU, and 0.157 μSv/h 0.152 μSv/h for 1000MU. 300MU of 10MV was 0.49 μSv/h, 0.309 μSv/h, and 0.69 μSv/h, 0.416 μSv/h for 600MU, respectively, and 1000MU was 0.977 μSv/h and 0.478 μSv/h, respectively. The 300MU of 15MV was 3.02 μSv/h, 1.2 μSv/h, 5.459 μSv/h at 600MU, 7.34 μSv/h at 1.836 μSv/h 1000MU, and 2.709 μSv/h. The average spatial dose rate of 6MV was not significantly different from the natural spatial dose rate in the treatment room. High spatial dose rates were measured at 10 MV and 15 MV and were attenuated over time. Therefore, entering the treatment room after a certain period of time (more than 60 seconds) is considered to be effective to prevent the exposure dose of radiation workers.
Park, Ki-Tae;Lee, Eun-Sung;Jung, Dong-In;Yeon, Seong-Chan;Lee, Hee-Chun
Journal of Veterinary Clinics
/
v.30
no.4
/
pp.264-267
/
2013
Stroke volume (SV) is an important parameter for monitoring of a critically ill animal and is echocardiographically measured using the modified Simpson's method, automated contour tracking (ACT) method and left ventricular outflow method. The purpose of this study was to evaluate the effect of anesthesia (isoflurane) on the SV during echocardiographic examination and to evaluate the feasibility of ACT method for measuring the stroke volume without anesthesia (conscious state). Ten clinically healthy adult Beagle dogs (3 male and 7 female, weighing 6.6-10.8 kg, aged 2-3 years old) were enrolled. Our study found that the dogs anesthetized have a significantly lower SV, compared to the SV of dogs unanesthetized, regardless of methods measuring SV. In addition, in the dogs without anesthesia, the SV measured by ACT method was significantly lower than the other two methods. This result implies that the anesthesia may significantly lower the SV. Thus, the measurement of SV under anesthesia may not be adequate in veterinary field. Furthermore because the ACT method measured SV significantly lower than other two methods, this method may be inappropriate for measuring SV in even conscious dogs.
This study was undertaken to estimate the exposed dose of the medical personnel during the intracoronary radiotherapy procedure as a part of ongoing SPARE (Seoul National University Hospital Post-Angioplasty Rhenium) trial. Data of thirty-four patients among forty-two irradiated patients participating in this trial due to coronary artery stenosis were retrospectively analyzed. Intracoronary radiotherapy was delivered to the patient immediately after angioplasty ballooning. Prescribed dose was 17 Gy to media of the diseased artery and was delivered with $^{188}Re$ filled balloon catheter. Dosimetry was carried out with GM counter at eight different points. Ten centimeter and forty centimeter from the patient's heart were selected to represent maximum and whole-body exposed dose of the operator, respectively. Median delivered dose was 111.6 mCi with average treatment time of 576 seconds. Average exposed dose rate at 10 cm and 40 cm from the patient's heart were 0.43 mSv/hr and 0.30 mSv/hr, respectively. Average exposed doses per treatment were 0.07 mSv and 0.05 mSv for 10 cm and 40 cm from the patient's heart, respectively. Exposed doses measured are much lower than recommended limit of 50 mSv for radiation workers or 1 mSv for general population in ICRP-60. This study proves that current method of intracoronary radiotherapy incorporated in this trial is very safe regarding radiation protection.
Journal of Korean Academy of Oral and Maxillofacial Radiology
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v.25
no.1
/
pp.27-38
/
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).
Ji, Yoon-Sun;Lee, Nam-Sun;Kil, Ki-Jung;Yoo, Ji-Hyun
The Korea Journal of Herbology
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v.34
no.1
/
pp.109-116
/
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.
This study was performed randomly from all the patients who visited the University Hospital in Gyeonggi-do from January 1, 2018 to June 30, 2018 for the abdominal CT scan. We divided the patients into three groups and evaluated the extent of effective dose and image quality according to the area of the abdominal CT image. As a result, the effective dose was 7.34 mSv in the average area group, 8.39 mSv in the average area and 5.89 mSv in the average area. For the analysis of image quality, ROI was plotted in the same three regions according to the abdominal area. As a result, CT values were significantly different in the abdominal area classified into 3 groups (p <0.05). The results of this study can be used as a basic data for the development of a protocol that can be applied in actual clinical practice. It is thought that it can help to reduce the image quality and the radiation dose.
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.
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