• Journal of the Korean Society of Radiology
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• v.9 no.1
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• pp.17-21
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• 2015

Recently, As people's interest in the health of teeth is increased in the medical field changed into aging society, the number of times for the radiological diagnosis is increased. It can be said that the radiation exposure dose of Korean population is increased. It is also growing concern about radiation exposure. Therefore, the basic data for the dental panoramic X-ray system, its investigation and measuring the radiation dose is needed. In this study, we used ALOKA PDM-117 dosimeter and estimated a two-dimensional dose distribution of the dental panoramic X-ray system (VATEC Pax-400). Dose evaluation about the distribution is confirmed from the point of radiation exposure of a patient. Dose distribution of the dental panoramic X-ray system irradiated chin and the facial region to high dose as well as the parts of teeth. It was founded that the eye lens which are sensitive to radiation are exposed to unnecessary radiation, considering the effect of scattered radiation. The results of this study will be used more accurate dose assessment in a variety of object size and location of measuring dose.

• Nuclear industry
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• no.1_2 s.5
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• pp.21-26
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• 1982

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.429-434
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• 1996

소각 또는 고온용융 등의 열처리 설비의 운전시 이로부터 예상되는 작업자 및 인근주민의 방사선 피폭을 보수적인 개념과 단순화시킨 피폭예측 식을 이용하여 산출해 보았다. 200kg/hr 용량의 소각로에 대해 발전소의 가연성 폐기물을 소각하는 경우 작업자의 피폭이 인근주민보다 훨씬 우려해야 하는 영향인자였으며 소각대상물 중의 핵종농도의 제한, 소각재 취급시 차폐의 증대 등이 요구된다. 따라서 작업자의 최대 피폭허용기준치를 기초로 폐기물내 핵종의 최대 허용 비방사능치를 계산해 보았고 각 핵종의 영향도를 제시해 보았다. 적용된 식은 각종처리 및 처분시설의 설계 및 운전전에 안전성 평가에 활용될 수 있으리라고 기대된다.

• Journal of Radiation Protection and Research
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• v.30 no.1
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• pp.17-25
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• 2005

Since the safety of nuclear power plant has been becoming a big social issue the exposure dose of radiation for workers has been one of the important factors concerning the safety problem. The existing calculation methods of radiation dose used in the planning of radiation work assume that dose rate does not depend on the location within a work space thus the variation of exposure dose by different work path is not considered. In this study, a modified numerical method was presented to estimate the exposure dose during radiation work in radwaste storage considering the effects of the distance between a worker and sources. And a new numerical algorithm was suggested to search the optimal work path minimizing the exposure dose in pre-defined work space with given radiation sources. Finally, a virtual work simulation program was developed to visualize the exposure dose of radiation doting radiation works in radwaste storage and provide the capability of simulation for work planning. As a numerical example, a test radiation work was simulated under given space and two radiation sources, and the suggested optimal work path was compared with three predefined work paths. The optimal work path obtained in the study could reduce the exposure dose for the given test work. Based on the results, tile developed numerical method and simulation program could be useful tools in the planning of radiation work.

• Journal of radiological science and technology
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• v.40 no.4
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• pp.557-565
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• 2017

This study was conducted to investigate the radiation protection, awareness, and attitude of radiological technologists in the mammography room due to the low energy use of breast imaging. Data collection was performed by 222 independent radiological technologists in the breast and breast clinic of six hospitals except Jeju Island. The independent sample t-test and oneway variance analysis were performed. As a result, it was found that the lower the number of men(p<0.05), the age of 30s(p<0.05), the marriage(p<0.05), the work experience of more than 10 years(p<0.05), the working hours of 8 hours(p<0.01), the less the impact of radiation(p<0.01), the more important it was to radiation defense. appear. This is thought to be influenced by the work specificity and work environment of the mammography room, and it will be used as a basic data to raise awareness and act on the exposure through analysis with other factors.

• Journal of Radiation Protection and Research
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• v.32 no.3
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• pp.111-115
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• 2007

A deuterium oxide leakage accident occurred on October 4, 1999, at nuclear power plant in Korea. The concentration of tritium in air increased and 22 workers were exposed by tritium at that time. It is well known that tritium causes internal exposure. Therefore, we examined complete blood cell count, physical and biological dosimetry fur 13 workers among whole 22 workers to check the health effect and to evaluate the dose estimation of tritium exposure. The leukocyte count test, one of general blood test, was normal. The estimated doses were 0 - 4.44 mSv by physical dosimetry and 0-37 mGy by biological dosimetry. This dose does not exceed radiation dose limit, and the clinical symptoms of the exposed workers were not shown. The consistency between clinical sign and estimated dose means that physical and biological dosimetry were very useful especially in accident evaluation.

• Journal of the Korean Society of Radiology
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• v.17 no.2
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• pp.249-255
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• 2023

In this study, radiation exposure doses were measured in the course of clinical practice of radiation workers, radiological technologists in the radiation-related worker group, and preliminary-radiological technologists who were classified as frequent visitors. Radiological technologists who worked in the radiation area of C University Hospital in Incheon for a year from January 2021 and 121 students who completed clinical practice at the same medical institution from July 1 to August 31 were the subjects of the study. The nominal risk factor based on ICRP 103 was used to evaluate the probability of side effects due to the exposure dose to the lungs, which are organs at risk of damage due to radiation exposure dose. During the clinical practice period, radiology students, who were classified as frequent visitors, had a surface dose of 0.98 ± 0.14 mSv and a deep dose of 0.93 ± 0.14 mSv. In other words, 6.7 per 1,000,000 for shallow dose and 6.4 per 1,000,000 for deep dose were found to have side effects due to exposure to the lungs. This is a value in terms of exposure dose in one year. Considering that the radiation (science) education course is 3 or 4 years, systematic management and attention to prospective radiation workers who are going to clinical practice are required, and the stochastic effect of radiation In relation to this, it is considered that it will be used as basic data for radiation safety management.

• Journal of radiological science and technology
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• v.34 no.1
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• pp.59-64
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• 2011

We investigated the radiation exposure caused by DIPS, which is used to identify accurate repositioning and tumor location in pediatric cancer patients proton therapy. To compare and analyze DIPS condition, 50 pediatric cancer patients who underwent proton therapy were selected in Ilsan K cancer-specialized hospital from March 2007 to October 2009. For DIP exposure, 0.09~1.57 mGy is measured in AP and lateral directions and 23.55 mGy is measured in CSI patients. In whole brain patient, the amount of a day DIP exposure dose was 1.13 mGy. During treatment period, who exposed the biggest DIP dose are whole brain patients, 632.71 mGy is exposed. It is 1.13% of prescribed dose, represented dose is adequate because it is not exceeded 2% of recommended dose. Even though the exposed dose is not exceeded more than 2% of prescribed in DIP exposure, we should recognize the radiation damage and genetic influences to pediatric cancer patients, who is much sensitive to radiation and has longer mean residual life time. Therefore, DIPS guideline for pediatric cancer patients should be indicated to minimize the radiation exposure.

• Journal of the Korean Society of Radiology
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• v.10 no.7
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• pp.495-502
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• 2016

In this study, we analyzed the effects of radiation exposure, as compared to the hematological parameters change of medical radiation workers and the public. The mean value of all hematological parameters were in the normal range. Eosin mean value of the radiation workers($2.52{\pm}1.79%$) showed that a significantly lower than the control group($2.92{\pm}1.39%$). In the comparison of the results depending on the occupation period, it showed high value that the mean of the radiation workers group WBC, platelet, Lymph, Mono, Baso. Over 20 years of radiation workers WBC, Mono showed low values and less than 10 years of radiation workers mean value of Baso showed low values, there was no statistical significance. In the comparison of the results depending on the 4 years cumulative radiation dose, Over 5.0 mSv of Radiation works RBC($4.61{\pm}0.53$ vs $4.91{\pm}0.38$), Hct($41.51{\pm}4.07$ vs $43.97{\pm}3.40$), Eosin($1.74{\pm}1.14$ vs $2.92{\pm}1.39$) showed low value, it was statistical significance. 0.5~1.0 mSv radiation exposure workers Hb ($13.93{\pm}1.75$) showed a significantly lower value than that of the control group ($14.90{\pm}1.29$).

• Journal of the Korean Society of Radiology
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• v.13 no.4
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• pp.667-674
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• 2019

Because examination with technegas produces images through simple diffusion accumulation, the examination room can become contaminated after scan. Therefore, radiation workers and patients awaiting examination will be affected by internal exposure from technegas inhalation. Before and after gravity ventilation, I am trying to find a way to reduce the exposure dose of waiting patients according to a comparative analysis of horizontal spatial dose rates over time. Spatial dose ratio were measured for 10 minutes from various distances and angles around ventilator's location before and after gravity ventilation. Then, mean values, standard deviation and reduction ratio were calculated. The highest reduction rate of gravity ventilation was 95.31% and the highest reduction ratio was 1 to 3 minutes. Therefore, the gravity ventilation could reduce the exposure dose of radiologic technologists, waiting patients, patient guardians and nurses. In conclusion, the reduction of the exposure dose during the technegas ventilation study through gravity ventilation will play a role in optimiging the protection and it is in accordance with the recommended reduction of the medical exposure by ICRP 103.