• Journal of the Korean Society of Radiology
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• v.5 no.6
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• pp.415-420
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• 2011

The purpose of this study is to know the exposure dose nearby table on the general radiography(skull AP, chest PA, abdomen AP, lumbar lateral, hip joint, knee joint) and to find the reducing it. We measured beside the 45cm and 75cm table center, and 70cm, 80cm, 130cm, 150cm height from the bottom. That were measured highly from the radiography of lumbar lateral, abdomen AP and hip joint as followed $66.21{\mu}Sv$, $34.22{\mu}Sv$, and $32.35{\mu}Sv$ at the 80cm height beside 45cm from the center of table. Measured doses were reduced in order of chest PA, abdomen, hipjoint, skull, knee joint projection. It appears exposure dose of nearby radiographic table was extremely low amount compared with limit of dose(1mSv). If it protected by Pb apron, exposure dose of assisting person will not be exceed a limit of dose. Conclusively, Wearing apron is very important to avoid radiation from the general radiography.

• Journal of the Korean Society of Radiology
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• v.13 no.2
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• pp.291-296
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• 2019

Nuclear medicine have often used to diagnose cancers. The main absorbed dose from radiation to a radiation worker resulted from open radioisotopes. Methods for reducing the radiation dose to a radiation worker from radioisotopes injected to patients were studied. The shield device of 0.2 mmPb was manufactured as a size of $300mm{\times}500mm{\times}150mm$. By using dosimeters of Nanodot, the absorbed doses for thyroid, chest and genital organ were measured with and without a shielding device and with syringe shield and shielding device together. The highest absorbed dose of 0.908 mGy reduction of 20.8% as 0.719 mGy was in the genital organ by using the syringe shield and a shielding device together. A effective dose for a radiation worker during 1 year was expected to 1.223 mSv at the chest, which was decrease as 0.994 mSv by shielding device and syringe shield together. When open radioisotope is injected to a patient for examination, the only use of a shielding device results in the reduction of radiation dose to radiation workers.

• Journal of Radiation Protection and Research
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• v.28 no.3
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• pp.207-213
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• 2003

Carbon-14 is one of the major radionuclides released by CANDU Nuclear Power Plants(NPPs). It is almost always emitted as gas through the stack. From CANDU NPPs about 95% of all carbon-14 is released as carbon dioxide. Carbon-14 is a low energy beta emitter which, therefore, gives only a small skin dose from external radiation. As carbon dioxide Is physiologically rather inert gases for man's metabolism, the inhalation dose is probably less than 1 % of the ingestion dose. But this source of carbon-14, formed in a closed, nor-oxidative environment, was subsequently released into the workplace as an insoluble particulate when these systems were opened lip for re-tubing at CANDU NPPs. As a part of the improvement of dosimetry program at Wolsong Nuclear Power Plants, the carbon-14 metabolism based on references was investigated and studied to setup the internal dosimetry program due to inhalation of carbon-14.

• Journal of Radiation Protection and Research
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• v.39 no.1
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• pp.61-64
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• 2014

Radioactive materials are in use and have many applications from the generation of electricity to the purposes of research, industry and medicine such as diagnosis and therapy. In the course of their use some of radioactive substances may be discharged into the environment from facilities using the unsealed radioactive materials, which are main artificial sources occurring the public exposure. Discharges are in the form of gases, particles or liquids. This paper provides procedures to estimate the level of the public exposure based on the conservative assumptions and simple calculations in the facility using unsealed liquid sources. They consist of two processes; (1) to calculate maximum concentration of gaseous effluents discharged through the exhaust pipe and average concentration of liquid effluents discharged through the drain of the storage tank, (2) to compare each of them to numerical guidances for the discharges of radioactive gaseous and liquid effluents mentioned in the related notification. For this purpose followings are assumed properly; daily usage, form and dispersion rate of radionuclides, daily amount of radioactive liquid waste and exhaust and drainage equipment. The procedures are readily applicable to evaluate environmental effects by planned effluent discharges from facilities using the unsealed radioactive materials. In addition they may be utilized to obtain practical requirements for radiation safety control necessary for the reductions of the public exposure.

• Journal of the Korean Society of Radiology
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• v.5 no.5
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• pp.245-253
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• 2011

The hazard level will be increased with the augmentation of the dose received by patients. Therefore, patients radiation dose have been analyzed by this study for the radiology clinics located at Seoul and Gyeongin area from August 2009 to September 2010. In the case of the front and rear directional inspection of skull, patient radiation dose was turned out to be 1.75mGy for radiology clinic, 3.00mGy for UK, 3.00mGy for Japan, and 5.00mGy for Germany, therefore, radiology clinic was the lowest. In the case of lateral directional inspection of skull, patient radiation dose was turned out to be 1.49mGy for radiology clinic, 1.50mGy for 3rd medical institution, therefore, radiology clinic was measured lower, and it was lower than 3.00mGy which is the recommended dose of IAEA. In order to reduce medical exposure of patient, optimization of efficient protection of radiation and reduction of medical radiation exposure are thought to be required by observing recommendation of international organization based on the result of this study.

• Journal of Radiation Protection and Research
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• v.40 no.4
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• pp.211-215
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• 2015

In case of radiation emergencies, radioactive materials released into environments can cause internal exposure of members of the public. Even though whole body counters are widely used for direct measurement of internally deposited radionuclides, those are not likely to be used at the field to rapidly screen internal exposure. In this study, we estimated the counting efficiencies of portable NaI detector for different size BOMAB phantoms using Monte Carlo transport code to apply handheld gamma spectrometers for rapid screening of internal exposure following radiological accidents. As a result of comparison for two counting geometries, counting efficiencies for sitting model were about 1.1 times higher than those for standing model. We found, however, that differences of counting efficiencies according to different size are higher than those according to counting geometry. Therefore, we concluded that when we assess internal exposure of small size people compared to the reference male, the body size should be considered to estimate more accurate radioactivity in the human body because counting efficiencies of 4-year old BOMAB phantom were about 2.4~3.1 times higher than those of reference male BOMAB phantom.

• Journal of the Korean Society of Radiology
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• v.13 no.2
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• pp.147-151
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• 2019

In chest and abdomen CT scans, the radiation exposure doses by scattering lines were measured at the eyeball and thyroid. Radiation exposure was investigated by using shielding devices. The chest and abdomen CT scan protocols used in the real examination were applied to measure and compare radiation doses before and after the use of shielding devices at the eyeball and the thyroid. The radiaton doses were measured with OSLD dosimeters. Barium, tungsten sheets, goggles and neck shields were used to protect the scattered X-ray. The chest CT scans showed respectively 3.01 mSv and 6.21 mSv at the eyeball and the thyroid by the scattered X-ray. The abdomen CT scans showed 0.55 mSv and 3.22 mSv for the eyeball and the thyroid respectively. Barium and tungsten sheets had 11% to 13% protection rates at the eyeball and the thyroid for chest CT scan, and 34% to 49% reduction in radiation dose for the abdomen CT scan. Because of the significant radiation dose, which causes cataracts and thyroid cancer by the repeated and continuous radiation exposure, for the chest and the abdomen CT scans, it is required to use shielding devices to reduce radiation dose for examinations.

• Journal of the Korean Society of Radiology
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• v.15 no.3
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• pp.355-359
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• 2021

In this study, the purpose of this study was to analyze the degree of exposure of radiation workers assigned to the Department of Radiology and frequent visitors during on-campus practice, and to conduct a basic study on the feasibility and optimization of the radiation protection of the Nuclear Safety Act for the Department of Radiology. . The average exposure dose of occupational workers by year was 0.01 mSv, the lowest in 2014 and 2016. The highest figure was 0.12 mSv in 2018. The average exposure dose of frequent visitors by year was the lowest at 0.013 mSv in 2018, and the highest at 0.022 mSv in 2016. According to this study, the annual exposure dose received by professors, practical assistants, and students in the department of radiology (department) who use only radiation generators in the course of in-school practice is less than 1 mSv, which is the dose limit for the general public. Therefore, at the time when the radiation dose of students in the Department of Radiology is lower than the dose limit of the general public, the current safety regulation of the Nuclear Safety law is judged to be excessive regulation. Therefore, it is considered necessary to revise the regulations for radiation generators in the current Nuclear Safety law or to revise the radiation safety management system for university students.

• Journal of radiological science and technology
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• v.38 no.2
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• pp.101-106
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• 2015

Recently, There has been a growing interests in exposure dose to the patient who take a examination using radiation. The radiological technologists should be concerned about the exposure dose to patients and make an efforts to reduce the patient dose without decreasing the image quality. In the case of foreign, the exposure dose of general X-ray examination have been managed by standard value of exposure dose using dose area product (DAP) and entrance surface dose (ESD) dosimeter. This study is to compare DAP and ESD in skull anterior posterior (AP), chest posterior anterior (PA), and abdomen AP projections of phantom by using DAP and ESD dosimeter. In the results, there were no differences between DAP and ESD dosimeter.

• Proceedings of the Korea Air Pollution Research Association Conference
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• 2003.05b
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• pp.67-68
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• 2003

라돈은 일반적으로 가장 잘 알려진 천연 방사성핵종 중 하나로서 무향 무색의 불활성기체이며 붕괴과정에서 알파입자를 방출한다. 라돈에 의한 피폭선량은 라돈붕괴에 의해 생성된 라돈자손이 호흡기관 표면에 침착되어 방출하는 알파선에 기인한다. 따라서, 피폭선량에 주로 기인하는 것은 라돈 자신이 아니라 그의 단 반감기 라돈자손들이다. 이처럼 라돈은 잘 알려진 폐암 유발원으로서 고농도의 라돈에 장기간 노출되는 경우 폐암을 유발할 수 있다. UNSCEAR 보고서(1993)는 자연 환경중에서 인간이 받는 연간 총 피폭선량인 2.4 mSv중 약 50%에 해당하는 1.15 mSv가 라돈과 그 자손에 의한 것이며 대부분 옥내에서의 호흡에 의해 비롯된다고 평가하고 있다. (중략)