• 한국방사선학회논문지
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• 제15권3호
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• pp.355-359
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• 2021

본 연구에서는 교내 실습 중 방사선(학)과 에 지정된 방사선작업종사자 및 수시출입자의 피폭 정도를 분석하여 방사선(학)과에 대한 원자력안전법의 방사선 방호에 대한 타당성과 최적화에 대한 기초 연구에 목적을 두었다. 연도별 작업종사자의 평균 피폭선량 2014년과 2016년에 0.01 mSv로 가장 낮은 수치가 나타났으며. 가장 높은 수치는 2018년도로 0.12 mSv이다. 연도별 수시출입자의 평균 피폭선량은 2018년 0.013 mSv로 가장 낮은 수치를 보였으며, 2016년 0.022 mSv로 가장 높은 수치가 나타났다. 본 연구를 통하여 방사선 발생장치만을 사용하는 대학의 담당교수, 실습 조교 및 방사선(학)과의 학생들은 교내실습 과정에서 받는 연간 피폭선량은 일반인의 선량한도인 1mSv에도 미치지 못하는 수준이다. 그러므로 방사선(학)과 학생들의 피폭선량이 일반인의 선량한도 보다 낮게 나오는 시점에서 현재 원자력안전법의 안전규제는 과도한 규제라고 판단된다. 따라서 현재의 원자력안전법에서 방사선 발생장치의 규정을 개정하거나 대학의 재학생에 대한 방사선안전관리 체계를 수정하는 것은 필요하다고 사료된다.

• 대한방사선기술학회지:방사선기술과학
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• 제45권1호
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• pp.69-76
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• 2022

This study, the method of reducing the exposure dose by changing the geometrical requirements among the preceding studies and the method of directly wearing a protector on the patient were used to expose the patient. A comparative experiment was conducted on the method of reducing the dose and the most effective method for reducing the exposure dose was investigated. Using the phantom, the dose of the lens, thyroid gland, and gonad gland in the 5 views most used in coronary angiography and intervention accumulated 5 times for 10 seconds at 60~70 kV, 200~250 mA as an automatic controller of the angiography system, and measured by Optically Stimulated Luminescent Dosimeter(OSLD). SID 100 cm and Cine 15 f/s as a control group the experiment was conducted by dividing the experimental group into 3 groups: a group lowered to Cine 7.5 f/s, a phantom protector, and a group lowered to 95 cm SID. As a result of the experiment, showing decrease in exposure dose compared to the control group. Lowering the cine frame may be the simplest and most effective method to reduce the exposure dose, but there is a limit that it cannot be applied if the operator judges that the diagnostic value is small or feels uncomfortable with the procedure. Conclusion as fallow reducing the exposure dose by directly wearing protector is the next best solution, and it is hoped that the conclusions obtained through this study will help reduce the exposure dose to unnecessary organ.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.1372-1377
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• 2003

The stabilization of propane/air lean premixed flames by a heated cylindrical rod is investigated experimentally. The flame stability limits, heat flux, surface temperatures, equivalence ratios, and mixture velocities are measured in order to understand the role of heat flux or surface temperature on the flame stabilization of lean premixed flames. The flame stability limits are lowered by a heated cylindrical rod and extended even below the flammability limit of propane/air mixture when sufficient heat flux is provided. The flame stability limit decreases with the increase of heat flux or surface temperature and decreases with the higher mixture velocity. The diameter of cylindrical rod, however, dose not significantly affect the flame stability limit. The laminar flame speed has been measured for ultra lean propane/air premixed flames. The flame stabilization by a heated cylindrical rod provides the useful tool for the measurement of flame speed under very fuel-lean conditions.

• 디지털산업정보학회논문지
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• 제10권3호
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• pp.41-48
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• 2014

This paper provides the design of system software for the management of radiation dose that is generated by using computerized tomography(CT). Recently, the radiation leakage incident of Japanese nuclear power plant was in the news internationally and there is a growing interest not only in nuclear power plant but in medical radiation exposure. In spite of the fact that currently safety management of radiation is under control only the workers of the radiation involved, now the exposure management of patients have been required. As surgery and inspections using the radiation have increased, this medical radiation exposure is increasing too. But it is a real situation that medical institutions don't know the level of radiation exposure applied to the patient. Therefore, a system for managing the radiation exposure of a patient from the medical institution is required. This paper proposes a design of a software program that manages the radiation exposure of CT which is a 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 be of help to optimize the medical exposure of the patient.

• 한국안전학회지
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• 제8권4호
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• pp.165-174
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• 1993

For the safety assessment of the demonstration-scale incineration plant for treating the combustible radioactive wastes, radiation doses of a worker and a residential individual were estimated. The demonstration plant showed a good performance of trial-burn tests using non-radioactive tracers with resulting In high mass reduction of around 40 times and very low emmission of dusts through a stack, which promised a high decontamination factor in an order of 10$^{7}$ . Based on the result s obtained from the trial-burns in the process, the estimation of radiation dose for workers and general publics near the plant was made using dose pathway calculation theories. The parametric values for calculation were selected from design and operational results of the process and from more conservative conditions In reference data. The estimated annual doses for workers and residential indivisuals were 3.07 $\times$ 10$^{-4}$ and 4.35 X 10$^{-8}$ $\mu$Sv/y, respectively, which were high enough to operate the process when comparing with the allowable dose limit in the regulation. The dose calculation models were quite applicable with showing an excellent safety for the process.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1176-1179
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• 2019

Measurements of activity concentrations of radionuclides in atmospheric releases were performed in 2017-2018 at vent stacks of seven Russian nuclear power plants. The selected instruments and research methods, with detection limits significantly lower than the existing detection limit of Russian NPPs routine control, allowed to reliably determine up to 26 radionuclides. Analysis of experimental data allows to determine the list of radionuclides for calculation the effective dose rates to public and the permissible annual discharge levels for each Russian NPP. Radiocarbon is determined as major contributor for the dose from the atmospheric releases of LWGR reactors - up to 98% for EGP-6 and RBMK-1000 (Smolensk NPP) reactors. For PWR reactors (VVER) radionuclides contribution to the annual dose from atmospheric releases is more complicated, but, in general, dose is formed by tritium, $^{14}C$ and noble gases. The special monitoring results with ranking of measured radionuclides according to their contribution to the effective dose makes it possible to optimize the list of controlled radionuclides in airborne releases of Russian NPPs from 94 to 8-16 for different NPPs.

• 방사성폐기물학회지
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• 제19권1호
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• pp.133-140
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• 2021

This study evaluates the radioactivity of concrete waste that occurs due to large amounts of decommissioned nuclear wastes and then determines the surface dose rate when the waste is packaged in a disposal container. The radiation assessment was conducted under the presumption that impurities included in the bio-shielded concrete contain the highest amount of radioactivity among all the concrete wastes. Neutron flux was applied using the simplified model approach in a sample containing the most Co and Eu impurities, and a maximum of 9.8×104 Bq·g-1 60Co and 2.63×105 Bq·g-1 152Eu was determined. Subsequently, the surface dose rate of the container was measured assuming that the bio-shield concrete waste would be packaged in a newly developed disposal container. Results showed that most of the concrete wastes with a depth of 20 cm or higher from the concrete surface was found to have less than 1.8 mSv·hr-1 in the surface dose of the new-type disposal container. Hence, when bio-shielded concrete wastes, having the highest radioactivity, is disposed in the new disposal container, it satisfies the limit of the surface dose rate (i.e., 2 mSv·hr-1) as per global standards.

• 한국방사선학회논문지
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• 제5권6호
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• pp.415-420
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• 2011

본 연구는 방사선 일반 촬영시 촬영 도움자가 피폭받을 수 있는 테이블 주변의 산란선에 의한 피폭선량을 알아보고자 하였다. 두개부, 흉부, 복부, 요추부, 고관절, 그리고 슬관절 촬영시 테이블 중앙으로부터 옆으로 45cm, 75cm 떨어진 지점에서 바닥으로부터 70cm, 80cm, 130cm, 150cm 높이에서 산란선에 의한 피폭선량을 측정하였다. 측정결과 요추 측방향, 복부 정면, 그리고 고관절 촬영이 80cm 높이에서 $66.21{\mu}Sv$, $34.22{\mu}Sv$와 $32.35{\mu}Sv$로 가장 높은 피폭을 보였고, 흉부, 복부, 고관절, 두개부, 슬관절 순서로 선량이 감소하였다. 촬영 테이블 높이는 70cm 보다 80cm에서 대체로 높은 선량을 보였으며, 80cm 이상에서는 높이가 높아질수록 선량은 감소하였다. 측정된 선량들은 촬영 도움자가 납 방호복을 착용할 경우 일반인 연간 피폭선량한도인 1mSv와는 큰 차이가 있어 우려할 선량은 아닌 것으로 나타났다.

• Clinical and Experimental Pediatrics
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• 제58권3호
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• pp.77-83
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• 2015

Relative to a fetus of the same gestational age, very low birth weight (VLBW) infants are more likely to be underfed and to undergo growth restriction during their early hospital stay. The current trend towards "early and aggressive" nutritional strategies in VLBW infants aims to overcome the early nutritional deficiency and thereby boost postnatal catch-up growth, simultaneously improving long-term neurodevelopmental outcomes. Although the minimum starting amino acid (AA) dose to prevent negative nitrogen balance is well established, the upper limit and the rate of increase of early AA doses are controversial. Most randomized controlled trials show that early and high-dose (target, 3.5 to 4.9 g/kg/day) AA regimens, with or without high nonprotein calories, do not improve long-term growth and neurodevelopment. High-dose AA supplementation may lead to early metabolic disturbances and excessive or disproportionate plasma AA levels, particularly in infants of very low gestational age. Further large studies are needed to clarify the optimal strategy for early administration of parenteral AA doses in VLBW infants.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2019-2024
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• 2021

For evaluating the radiological safety of dismantled concrete, the process of disposal and recycling of the radioactive concrete generated during the dismantling of Kori Unit 1 is analyzed. Four scenarios are derived based on the analysis of the concrete recycling and disposal process, and the potential exposure to the workers and public during this process are calculated. VISIPLAN and RESRAD code are used for evaluating the dosages received by the workers and public in the following four scenarios: concrete inspection, transport of concrete by the truck driver, driving on a recycled concrete road, and public living near the landfilled concrete waste. Two worker exposure scenarios in the processing of concrete and two public exposure scenarios in recycling and disposal are considered; in all the scenarios, the exposure dose does not exceed the annual dose limit for each representative.