• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.206-207
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• 2010

• Journal of Radiation Protection and Research
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• v.31 no.2
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• pp.97-104
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• 2006

In recent years, the MOSFET dosimeter has been widely used in various medical applications such as dose verification in radiation therapeutic and diagnostic applications. The MOSFET dosimeter is, however, mainly made of silicon and shows some energy dependence for low energy Photons. Therefore, the MOSFET dosimeter tends to overestimate the dose for low energy scattered photons in a phantom. This study determines the correction factors to compensate these dependences of the MOSFET dosimeter in ATOM phantom. For this, we first constructed a computational model of the ATOM phantom based on the 3D CT image data of the phantom. The voxel phantom was then implemented in a Monte Carlo simulation code and used to calculate the energy spectrum of the photon field at each of the MOSFET dosimeter locations in the phantom. Finally, the correction factors were calculated based on the energy spectrum of the photon field at the dosimeter locations and the pre-determined energy and directional dependence of the MOSFET dosimeter. Our result for $^{60}Co$ and $^{137}Cs$ photon fields shows that the correction factors are distributed within the range of 0.89 and 0.97 considering all the MOSFET dosimeter locations in the phantom.

• Proceedings of the Korean Society of Medical Physics Conference
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• 2005.04a
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• pp.100-102
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• 2005

양성자 빔을 이용한 치료는 종양부위에 높은 선량을 균일하게 전달하고 정상세포에는 적은 선량을 전달할 수 있어 암치료 효과가 높으나 정확한 치료와 환자의 안전을 위해서는 양성자선량의 급락지점을 정확히 아는 것이 중요하다. 본 연구에서는 양성자와 물질과의 핵반응으로 직각방향으로 방출되는 즉발감마선을 측정하여 양성자선량 급락지점을 측정할 수 있는 검출시스템을 몬테칼로 전산코드로 전산모사하였으며, 70MeV 단일에너지 빔과 최대에너지가 70MeV인 SOBP 빔을 모의피폭체인 물팬텀에 조사하고 검출시스템을 통해 직각방향으로 방출되는 즉발감마선의 분포를 계산하였다. 모의피폭체 안에서의 양성자선량의 분포와 측정된 즉발감마선의 분포를 서로 비교하여 두 분포 사이의 상관관계를 찾고 이 상관관계를 이용하여 양성자선량 급락지점을 결정할 수 있음을 확인할 수 있었다.

• Journal of Radiation Protection and Research
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• v.25 no.4
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• pp.191-195
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• 2000

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.

• Nuclear Engineering and Technology
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• v.19 no.2
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• pp.99-106
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• 1987

Comparison study on the radiological effects by radionuclides from hypothetical 1,000MWe coal-fired power station and nuclear power plant is made. This paper describes the radiological effects only for gaseous effluents released in normal operation. Source terms for coal-fired Power station are quoted from foreign data and those for nuclear power plant are calculated for reference power plant. Gaussian plume model is used to assess atmospheric dispersion of radioactive effluents based on one year meteorological data of Kori site and individual doses are calculated at the maximum X/Q point. Doses from nuclear power plant are slightly more than those from coal-fred power plant. In the case of coal-fired power plant, doses by ingestion of contaminated vegetation are 73.5% of total doses.

• Journal of Radiation Protection and Research
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• v.39 no.2
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• pp.89-95
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• 2014

In potential accident consequence assessments for the licensing approval of LWRs, the ground deposition of radionuclides released into the environment is not allowed into the models, as recommended in the U. S. Nuclear Regulatory Commission's regulatory guide. Meanwhile, it is allowed into the assessment models for the licensing approval of PHWRs with consideration of more detailed physical processes of radionuclides in the atmosphere. Under these backgrounds, importance of exposure dose by ground deposition was quantitatively evaluated and comprehensively discussed. For potential accidental releases of $^{137}Cs$ and $^{131}I$, total exposure doses were more conservative in case of without consideration of ground deposition than in case of with its consideration. It was because of that the depletion of air concentration resulting from ground deposition is more influential in the contribution to total exposure doses than additional doses from contaminated ground. The exposure doses by the inhalation of contaminated air showed the contribution of more than 90% in total exposure doses, depending on atmospheric stability, release period of radionuclides and distance from a release point. The exposure doses from contaminated ground showed less than 10% at most in contribution of total exposure doses. The ratios of total exposure doses in case of with consideration of deposition to without its consideration for $^{131}I$ were distinct than those for $^{137}Cs$. As the atmosphere is more stable, release duration of radionuclides is longer, distance from a release point is longer, it was more distinct.

• Journal of radiological science and technology
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• v.33 no.2
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• pp.149-154
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• 2010

Exposed doses to the patient's caregiver and their house due to the 131I from patients discharged from the hospital were measured using OSL dosimeters. Usually, 3.37-5.55 GBq (100-150 mCi) of $^{131}I$ administrated patients are discharged from the hospital after 3 or 4 days of hospitalization in Korea. In addition, after 5 to 8 days, the accumulated doses of the patient's caregiver and house after hospitalization of the patient were measured using OSL dosimeters. The results of the measured average accumulated doses were 0.1 mSv, which is 10% of 1 mSv, the public dose limit in the Korean Atomic Energy Law. And it's standard deviation was 0.087 mSv. Based on the results of this study, we anticipate that we could assure the compliance of the regulation requirement 5 mSv of MEST (Ministry of Education, Science and Technology) Notice No. 2008-45 for the patient's caregiver or family, even if we reduce the 3-4 days of hospitalization to 1-2 days or less.

• The Journal of the Korea Contents Association
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• v.11 no.10
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• pp.349-354
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• 2011

The results of the scattery distribution in the fluoroscopy X-ray room were as follows. When the measurement was done at the same height with the table, measured value was 0.78 mGy/min ~ 0.04 mGy/min (95%) within 50 cm and 250 cm. At 50 cm below the table, it was 0.17 mGy/min ~ 0.02mGy/min (86%) and at 50 cm above the table was 1.37 mGy/min ~ 0.05 mGy/min (96%), displaying a decrease. At the same time, the amount of rays were reduced in 50 ~ 60% at the same height with the table than the location 50 cm above the table, 90~95% of reduction rate was observed at 50 cm below the table. For the collimator, comparing to the case when it was completely open, the amount of ray was reduced from 0.78 mGy/min to 0.16 mGy/min at 50cm away and 0.04 mGy/min to 0.01 mGy/min at 250cm away thus approximately 80% on average was reduced when the collimator was reduced to 25%. Comparing with the case when there was a object on the table, the amount of scatter ray was reduced by 96.7% at every location when there is not a object on the table.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.1
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• pp.23-30
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• 2005

From measured results of the neutron fields at some principal places within the containment building in a CE type nuclear power plant in operation, the radiation exposure of a worker to the neutron at there was evaluated and the equivalent dose reflecting new recommendation (ICRP 60) was compared with that doing the old one (ICRP 26). The measured neutron field was also compared with calibration neutron field. From the analysis, the following conclusion was obtained: the average neutron radiation weighting factor according to new recommendation is 2.41 to 2.71 times higher than the old one. The average neutorn radiation weighting factor at the measured place was similar to that at calibration neutron field. The average neutron energy at measured place was between 42 and 158 keV and higher than that of calibration field of 500 keV. So, the measured equivalent dose in nuclear power plant could be overestimated compared to the real equivalent dose.

• Journal of the Korean Society of Radiology
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• v.7 no.3
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• pp.175-179
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• 2013

To find out the appropriate defensive measures for protectors and radiation workers in rotating radiation generating devices such as CBCT and panorama, irradiation dose depending on the position was compared and analyzed. The devices such as panorama DP-90-P PAX-500 (Vatech, Korea) and CBCT DCT-90-P IMPLAGRAPHY Dental CT system (Vatech, Korea) were used. As irradiation dose measuring instruments, Ion chamber model 2026 and Reader 20X5-60E were used. The exposure conditions were set as the factor used in the clinical trial. The result of the experiment showed that panorama was the highest, 81${\mu}R$, at point A where the test starts first and the lowest, 53${\mu}R$, at point D where the test ends. In case of CBCT, it was the highest, 1,021${\mu}R$, at point D where the test ends and was measured as the highest, 809.67${\mu}R$, at point A where the test starts. If protectors and radiation workers are forced to examine a patient holding him, they should be positioned in the middle of the point where X ray tube starts to rotate and the point where it ends to avoid the position where radiation dose is the most. And due to the nature of equipment, it will be the safest for them to stand at the opposite side of the machine and to uphold it from the rear rather than upholding it from the side of a patient and they should wear appropriate the protection gear.