• Journal of radiological science and technology
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• v.34 no.4
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• pp.351-357
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• 2011

The $^{18}F$-FDG is one of the widely used isotopes for PET/CT scans. Dose amount injected to the patient depends on the characteristics of PET/CT systems. Obviously, the technologists who contact with patients would be exposed as well. In this study, we evaluated the exposed dose of the technologist who works on the PET/CT scanner. The exposed dose were measured every month with the TLDs from 6 technologists. Each technologist is shift-worker who manages 3 different PET/CT systems(Scanner 1(S1): 0.15 mCi/kg, Scanner 2(S2): 0.17 mCi/kg, Scanner 3(S3): 0.12 mCi/kg). The average exposed doses of technologists for each PET/CT system were measured as 0.76 mSv for S1, 0.93 mSv for S2 and 0.47 mSv for S3. The maximum dose was 1.12 mSv and minimum was 0.42 mSv. The results showed that there was a correlation between exposed dose and PET/CT system(p<0.005). Less injected dose for patient occurs less exposed dose for technologist. Various studies for the low dose PET/CT system are required for not only the patient but also the technologist.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2014.05a
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• pp.489-492
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• 2014

This thesis provides the design of system software for the management of radiation dose that is generated using computer tomography(CT). Because radiation exposure is different depending on the difference in sensitivity to each part for each of the patient's body, if we will be able to manage an appropriate amount of radiation, it is possible to estimate the radiation exposure of the patient as a result. Recently, radiation leakage incident of Japanese nuclear power plant was in the news internationally and there is a growing interest not only a nuclear power plant, to medical radiation exposure. In spite of the fact that currently safety management of radiation is under control only the workers of the radiation involved, exposure management of patients until now have been required. Surgery and inspection using the radiation in Korea will increase, due to this medical exposure has increased, but it is a reality that medical institution don't know the level of radiation exposure applied to the patient. Therefore a system for managing the radiation exposure of the patient from the medical institution is required. This paper proposes a design of a software program to manage the radiation exposure of CT is an typical imaging tool to use the radiation in the medical institution. By check the amount of radiation dose and set the limit of dose, we would help to optimize the medical exposure of the patient.

• Journal of the Korean Society of Radiology
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• v.17 no.2
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• pp.277-284
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• 2023

Since the radiological risk is different depending on the working environment, protection measures and policies must be developed through analysis of the field area environment. Evaluating the characteristics of the field area that uses radiation should be conducted through comparative analysis with other industries, not just the numerical value of the field area. In this study, evaluation factors were derived from exposure records by the department to compare radiation occupational exposure records by sector. And then, we developed a polygonal model for comparative analysis and applied them to eight work fields through ten evaluation factors. Based on the occupational exposure record in 2020, a polygonal model was applied to compare and evaluate the characteristics of the radiation work area. Through this, the usefulness of the polygonal model was confirmed, and protection policy measures for the industry were proposed.

• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.64-65
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• 2010

• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.242-243
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• 2010

• Korean Journal of Veterinary Research
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• v.41 no.1
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• pp.99-104
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• 2001

To determine if micronucleus (MN) assay could be used to predict the absorbed dose of victims after accidental radiation exposure, we carried out to assess the absorbed dose depending on the numerical changes of MN in human peripheral blood lymphocytes after $^{60}Co\;{\gamma}-rays$ exposure in the range of 0.25 to 1 Gy, respectively. The MNs were observed at very low doses, and the numerical changes according to doses. Satisfactory dose-effect calibration curve is observed after low dose irradiation of human lymphocytes in vitro. When plotting on a linear scale against radiation dose, the line of best fit was $Y=(0.02{\pm}0.0009)+(0.033{\pm}0.010)D+(0.012{\pm}0.012)D^2$. The dose-response curve for MN induction immediately after irradiation was linear-quadratic and has a significant relationship between the frequencies of MN and dose. These data show a trend towards increase of the numbers of MN with increasing dose. The number of MN in lymphocytes that were observed in the control group is $0.1610{\pm}0.0093/cell$. Accordingly, MN assay in human peripheral lymphocytes could be a useful in viva model for studying radio-protective drug sensitivity or screening test, microdosimertic indicator and radiation-induced target organ injury. Since MN assay is simple, rapid and reproducible, it will also be a biodosimetric indicator for individual dose assessment after accidental exposure.

• 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 Radiation Protection and Research
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• v.29 no.4
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• pp.237-242
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• 2004

The radioprotective effects of Melatonin and Ge-132 on acute hematopoietic injury was investigated in mice exposed to an acute whole-body radiation dose of 8 Gy. Melatonin was administered intraperitoneally 1 hour before irradiation at a dose of 200 mg/kg, and Ge-132 was administered orally from days 5 to 20 after irradiation at a dose 130 - 150 mg/kg/d. The radioprotective effects were evaluated for spleen using TUNEL assay, and in peripheral blood by counting lymphocyte & WBC. The 4 experimental groups (irradiation-only, melatonin pretreatment, Ge-132 posttreatment, and melatonin pretreatment plus Ge-132 posttreatment) were observed for survival analysis up to 30 days following irradiation. The apoptotic index (47.8% vs 45.9%, p=0.385), and the number of lymphocytes ($97/{\mu}{\ell}\;vs\;101/{\mu}{\ell}$, p=0.898) were not significantly different between the irradiation-only and the melatonin pretreatment group, But the number of WBCs ($147/{\mu}{\ell}\;vs\;306/{\mu}{\ell}$, p=0.010) was higher in the melatonin pretreatment group. The irradiation-only, melatonin, Ge-132, and melatonin plus Ge-132 treatments resulted in survival rate at 30 days of 21.4%, 100%, 35.7%, and 85.7%, respectively. The melatonin pretreatment group in survival analysis between groups was showed significantly higher survival than the irradiation-only(p=0.000), or Ge-132 posttreatment group(p=0.0003). These results indicate that the melatonin may have a potential as an effective radioprotector on acute hematopoietic syndrome following radiation exposure.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.10 no.7
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• pp.1760-1765
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• 2009

After administration of a radiopharmaceutical, the patient remains radioactive for hours or even days, representing a source of potential radiation exposure. Thus, including the personnel who are occupationally exposed to ionizing radiation, radiation exposure must be managed for members of the public, in particular for people accompanying patients. In this study we investigated radiation exposure dose management in the nuclear medicine departments at seven general hospitals. Two of them had no radiation safety considerations for patient transporters, sanitation workers and the like. And they all were careless of radioprotection for people accompanying patients. The average dose rate to people accompanying patients from radioactive patients just before a bone scan was 25.60 ${\mu}$Sv h-1. This is higher than 20 ${\mu}$Sv $h^{-1}$which is the annual public dose limit for temporary use. Therefore radiation dose measurement and risk assessment of patient transporters, sanitation workers and the like should be performed. And the nuclear medicine technologist should provide advices on the radiation safety to patient transporters, sanitation workers, people accompanying patients and so on. To ensure the radiation safety for people accompanying patients, it is required to restrict the patient's access to his relatives, friends and other patients or isolate patients.

• Journal of radiological science and technology
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• v.31 no.3
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• pp.217-222
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• 2008

Radiation dose to radiologists working at three hospitals in Seoul was investigated from Jan 1, 2006 to Dec. 31, 2006. The results are as follows. First, radiation dose to radiologists at a cardiac angiography room was measured as 1.41mSv, the highest while radiation dose to radiologists at a department of radiation oncology was measured as 0.64 mSv, the lowest. Second, radiation dose proves to be in direct proportion to the number of X-ray treatment. Third, as for the radiation dose in X-ray treatments, radiologists in cardiac angiography room are exposed to the largest amount of radiation while radiologists in diagnostic radiology department are exposed to the smallest amount of radiation. Last, radiation dose at a cardiac angiography room is the largest and is followed by nuclear medicine, diagnostic radiology, and radiation oncology departments in order. According to ICRP, exposure less than 20mSv per year is highly recommended while radiation dose is allowed as long as it is ranged less than 50mSv per year or 100mSv within a 5-year period. Taking into account the results, radiation exposure does not do any harm to radiologists at any related departments in Korean hospitals because the dose per year is less than 1.60mSv.