• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.584-589
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• 2003

The hot cell facility which is designed to permit safe handling of source materials with radioactivity levels up to 1,385 TBq, is planned to be built. To meet this goal, the facility is designed to keep gamma and neutron radiation lower than the recommended dose-rate in normally occupied areas. The calculations performed with QAD-CGGP and MCNP-4C are used to evaluate the proposed engineering design concepts that would provide acceptable dose-rates during a normal operation in hot cell facility. The maximum effective gamma dose-rates on the surfaces of the facility at operation area and at service area calculated by QAD-CGGP are estimated to be $2.10{\times}10^{-3}$, $2.97{\times}10^{-2}$ and $1.01{\times}10^{-1}$ mSv/h, respectively. And those calculated by MCNP-4C are $1.60{\times}10^{-3}$, $2.99{\times}10^{-3}$ and $7.88{\times}10^{-2}$ mSv/h, respectively The dose-rates contributed by neutrons are one order of magnitude less than that of gamma sources, and penetration and toboggan will be partly reinforced by lead shield.

• Journal of the Society of Disaster Information
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• v.18 no.4
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• pp.729-745
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• 2022

Purpose: This study collects basic data on the awareness of evacuation methods and evacuation facilities in the event of a radiological disaster of residents living in the emergency planning zone. Method: The residents of emergency planning zone were sampled using a random sampling method. A 1:1 interview was conducted using a structured questionnaire, and statistical analysis was performed using the minitab program. Result: First, the survey subjects showed a relatively low and negative awareness of the local government's work on radioactive disasters. Second, in terms of resident safety education, they had little experience in education, but they felt it was necessary and wanted education on evacuation methods, action tips, and the location of relief centers. Third, the location of the relief centers related to radioactive disasters was not well known, and there were many responses that they did not receive any guidance, and that they would be with their families when using the relief centers. Satisfaction levels were generally low with regard to the relief facilities. Fourth, the necessary priorities in preparation for radioactive disasters were education and training for radioactive disasters, facility supplementation, and supply of protective chemicals. Conclusion: The residents of emergency planning zone perceived the policies and tasks of the government or local governments relatively negatively in preparation for the occurrence of radioactive disasters, and their satisfaction was low. Regarding the matters pointed out as a priority, the government and local governments should publicize and educate the residents of accurate information and policies on radioactive disasters.

• Proceedings of the Korean Society of Broadcast Engineers Conference
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• 2017.06a
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• pp.40-43
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• 2017

본 논문은 딥러닝을 이용하여 대장통과시간(Colon Transit Time, CTT) 검사를 위한 단순복부 X-Ray 영상에서 방사선 비투과성 표지자(Radio-opaque Marker)를 자동으로 검출하는 기법을 제시한다. 대장통과시간 검사는 대장의 운동질환을 평가하는데 있어 가장 기본적인 방법으로 특히 만성 변비증 환자의 병태생리에 따른 유형 분류와 치료 계획을 설정하는데 큰 도움을 주고 있으며, 내과적 또는 외과적 치료 후 평가에도 유용한 검사이다. 대장통과시간 검사는 방사선 비투과성 표지자가 내재되어 있는 캡슐을 복용한 뒤 주기적으로 단순복부 X-Ray 촬영을 통해 구간별로 남아있는 표지자의 수를 세고, 이를 통해 구역별 통과시간을 측정한다. 이 과정에서 판독의가 직접 표지자의 위치 및 개수를 세기 때문에 많은 시간이 필요하게 된다. 따라선 본 논문에서는 이러한 단점을 보완하기 위해 딥러닝 기법을 사용하여 X-Ray 영상 내에서 표지자의 위치를 자동 파악하는 기법을 제시한다.

• Journal of Radiation Protection and Research
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• v.38 no.4
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• pp.237-241
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• 2013

The gamma energy distributions at the major working places during refueling outage of Korean PWR nuclear power plants were measured. In order to estimate the dose reduction effect of a lead vest, Monte Carlo calculation method was used. For the simulations, the MIRD-V phantom with a lead vest was formed and exposed to the measured radiation field. The average measured gamma energy is lower than that of standard which is generally applied to radiation protection procedures. For the efficient use of a lead vest and achievement of radiation protection purpose, it is necessary to estimate the energy distribution of radiation field at working places.

• Journal of the Korea Convergence Society
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• v.10 no.6
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• pp.89-94
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• 2019

This study will examine the awareness of students in radiology who have applied the reorganization of the safety management system of frequent visitors according to the amendment of the Nuclear Safety Act. A survey was conducted on 175 students from the Department of Radiology at K University. 98.1% of the students in the second grade, 90.3% in the third grade, and 97.7% in the fourth grade were recognized as need to be classified as person with frequent access by the Nuclear Safety Act. Limiting the operation of radiation equipment in radiography practice is a regulation that violates students' right to learn, and it is necessary to enact an exception rule for learning so that the right to study is not violated.

• Journal of Radiation Protection and Research
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• v.9 no.2
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• pp.76-89
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• 1984

Weighted committed dose equivalents($W_T\;H_{50}$) per intake of unit activity of four nuclides-I-131, I-133, Cs-134 and Cs-137-, which was based on the concepts of ICRP Pub. 30, are calculated for adult who is 70 kg and 25 years old and, for infant who is 10 kg and 1 year old. Metabolism of iodine taken through oral or inhalation pathway is described by using the three-compartment model which consists of inorganic, thyroid and organic compartment. After intake, the amount of iodine in every compartment is calculated by solving the transfer equations among the these compartments. As soon as caesium is taken into the body, it is distributed uniformly in the body through the transfer compartment. In this case, the amount of caesium in total body is calculated by using the total body compartment model which is divided into two tissue compartments because of their different biological half-lifes of caesium in body. As a result of calculations, whether oral or inhalation pathway, the values of ($W_T\;H_{50}$) per intake of unit activity of I-131 for infants are about ten times as much as those of adults. On the other hand, for Cs-134 and Cs-137, the values of $W_T\;H_{50}$ per intake of unit activity show that, whether adults of infants, they have almost the same values.

• Journal of Radiation Protection and Research
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• v.12 no.1
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• pp.40-47
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• 1987

The amount of the radionuclide release to the environment during a LOCA and its radiological consequence are assessed, for a 900MWe French PWR which is similar to the KNU 9/10, according to RFS V.1.a, in which the source term has been revised more conservatively after the TMI accident. The assessed result shows that the whole body and thyroid doses at the site boundary(500m) for 2 hours after the release are 66 mrem and 13.5 rem, respectively, and are within the corresponding limits. It is expected, however, that the thyroid dose would exceed the limit if the fraction of the organic iodine is over 10% of the iodine inventory.

• Nuclear Engineering and Technology
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• v.25 no.4
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• pp.561-569
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• 1993

DOT4.2-QAD-CG coupling method was used to analyze the dose rates outside the side and the bottom shield system of CANDU 6 plant. The average dose rates at the main airlock and the new fuel loading area are approximately 6 $\mu$Sv/h as it is required. The calculated dose rates have a good agreement with the measurements at the operating CANDU 6 plant. The method used in this paper can be applied to the radiation shielding analysis of Wolsong 2, 3, and 4 CANDU 6 type plants which will be constructed in the near future.

• Journal of radiological science and technology
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• v.44 no.4
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• pp.351-358
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• 2021

This research project is a program promoted to seek diversification of domestic radioactive waste analysis institutions, and seeks public development, win-win cooperation, and cooperation between the entrusted institution and the entrusted institution. Accordingly, the entrusted institution established a standard analysis procedure for establishing a quality control system for radioactivity analysis, establishing a radiation control zone, obtaining KOLAS accreditation, and performing proficiency tests, which are the performance ranges requested by the entrusted institution, and intersecting the radioactive isotope waste generated at the actual site. Verification was performed to confirm the analysis quality. In addition, facilities and equipment for radioactivity analysis were supplemented and expanded, and the basic technology foundation and technical skills were secured through securing professional technicians and education/training. It is judged that the entrusted institution will contribute to securing radiation safety through the smooth execution of treatment, disposal, and transportation through value creation and analysis of radioactive waste generated by radioactive isotope-using institutions (research institutes, hospitals, industries, etc.) by succeeding in this research project do.

• Journal of radiological science and technology
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• v.45 no.2
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• pp.159-164
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• 2022

The study developed a radiation dose measurement program in the radiology laboratory to measure how much exposure the students are exposed to during the radiology class, to request for the improvement and the revision of the current Nuclear Safety Act. The experimental program is shown in the following figure, and experiments were conducted to determine the degree of radiation exposure in the control room with a lead gown at a distance of 1 m, 2 m, and 1 m, and in a control room with a radiographic lead glass wall. The duration of the experiment was 3 months from April to June, when radiation imaging practice classes were conducted, and 128 hours of imaging practice per month were conducted. In order to find out the dose of radiation dose during radiology imaging practice class, the experiment was carried out from April to June for 3 months, and according to the program, the results of exposure dose were 0.34 mSv at 1 m distance, 0.01 mSv at shielding of lead gown at 1 m distance, 0.16 mSv at 2 m distance, and 0.01 mSv at control room with radiation lead glass wall. The exposure dose from the test results was much below the annual general public limit dose of 1 mSv. The restriction on the operation of the radiation equipment in the practice of the students is a regulation that infringes the right of students to learn, and amendments or exemptions of Nuclear Safety Act should be enacted to ensure that it does not violate the fundamental right to learn for students in radiology.