• 방사선산업학회지
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• 제10권1호
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• pp.29-35
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• 2016

Radiation generating devices must be properly shielded for their safe application. Although institutes such as US National Bureau of Standards and National Council on Radiation Protection and Measurements (NCRP) have provided guidelines for shielding X-ray tube of various purposes, industry people tend to rely on 'Half Value Layer (HVL) method' which requires relatively simple calculation compared to the case of those guidelines. The method is based on the fact that the intensity, dose, and air kerma of narrow beam incident on shielding wall decreases by about half as the beam penetrates the HVL thickness of the wall. One can adjust shielding wall thickness to satisfy outside wall dose or air kerma requirements with this calculation. However, this may not always be the case because 1) The strict definition of HVL deals with only Intensity, 2) The situation is different when the beam is not 'narrow'; the beam quality inside the wall is distorted and related changes on outside wall dose or air kerma such as buildup effect occurs. Therefore, sometimes more careful research should be done in order to verify the effect of shielding specific radiation generating device. High energy X-ray tubes which is operated at the voltage above 400 kV that are used for 'heavy' nondestructive inspection is an example. People have less experience in running and shielding such device than in the case of widely-used low energy X-ray tubes operated at the voltage below 300 kV. In this study, Air Kerma value per week, outside concrete shielding wall of various thickness surrounding 450 kVp X-ray tube were calculated using MCNP simulation with the aid of Geometry Splitting method which is a famous Variance Reduction technique. The comparison between simulated result, HVL method result, and NCRP Report 147 safety goal $0.02mGy\;wk^{-1}$ on Air Kerma for the place where the public are free to pass showed that concrete wall of thickness 80 cm is needed to achieve the safety goal. Essentially same result was obtained from the application of HVL method except that it suggest the need of additional 5 cm concrete wall thickness. Therefore, employing the result from HVL method calculation as an conservative upper limit of concrete shielding wall thickness was found to be useful; It would be easy, economic, and reasonable way to set shielding wall thickness.

• Radiation Oncology Journal
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• 제33권4호
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• pp.337-343
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• 2015

Purpose: The purpose of this report is to describe the proton therapy system at Samsung Medical Center (SMC-PTS) including the proton beam generator, irradiation system, patient positioning system, patient position verification system, respiratory gating system, and operating and safety control system, and review the current status of the SMC-PTS. Materials and Methods: The SMC-PTS has a cyclotron (230 MeV) and two treatment rooms: one treatment room is equipped with a multi-purpose nozzle and the other treatment room is equipped with a dedicated pencil beam scanning nozzle. The proton beam generator including the cyclotron and the energy selection system can lower the energy of protons down to 70 MeV from the maximum 230 MeV. Results: The multi-purpose nozzle can deliver both wobbling proton beam and active scanning proton beam, and a multi-leaf collimator has been installed in the downstream of the nozzle. The dedicated scanning nozzle can deliver active scanning proton beam with a helium gas filled pipe minimizing unnecessary interactions with the air in the beam path. The equipment was provided by Sumitomo Heavy Industries Ltd., RayStation from RaySearch Laboratories AB is the selected treatment planning system, and data management will be handled by the MOSAIQ system from Elekta AB. Conclusion: The SMC-PTS located in Seoul, Korea, is scheduled to begin treating cancer patients in 2015.

• 한국군사과학기술학회지
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• 제10권2호
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• pp.76-83
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• 2007

This report presents the test technique using optic thermal sensor for the HERO evaluation of equipment installed EED. The calibration method of EED-thermal sensor assembly is explained by relation between the current in bridge wire and voltage in thermal sensor. And the HERO test and evaluation method is indicated based on MIL-STD-464A and MIL-STD-331C. The safety and reliability levels of EED-thermal sensor assembly are evaluated when exposed in the electromagnetic environment.

• Journal of Radiation Protection and Research
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• 제47권4호
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• pp.204-213
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• 2022

Background: The accident at the Fukushima Daiichi nuclear power plant increased the level of anxiety related to the radioactive contamination of various foods sourced in Japan. Particularly, after the accident, the detection of artificial radionuclides in locally produced foods raised food safety concerns. In this study, the radioactivity concentrations and annual ingestions of ⁴⁰K and ¹³⁷Cs in food products commonly and frequently consumed by the general public were investigated, and the annual effective dose of each was evaluated. Materials and Methods: The 2016-2018 data from the Radiation Safety Management Report released by the Korea Nuclear Safety Technology Center was referenced for the evaluation of the amounts of ⁴⁰K and ¹³⁷Cs contained in food. Using the food-ingestion survey mentioned above as a reference, we selected 62 foods to include in our radioactivity concentration and dose assessment. We also developed a questionnaire and evaluated the responses from the subjects who answered the questionnaire. Results and Discussion: The radioactivity concentration of ¹³⁷Cs was found to be close to or below the level of minimum detectable activity. Additionally, the annual ingestion of 62 foods was 294.77 kg/yr, the effective doses from ⁴⁰K and ¹³⁷Cs were 136.4 and 0.163 μSv/yr, respectively. Conclusion: Thus, the findings confirmed that the effective dose from ⁴⁰K and ¹³⁷Cs in food tends to be lower than the effective dose limit of 1 mSv/yr suggested by the International Commission on Radiological Protection (ICRP) Publication 60. The questionnaire developed in this study is expected to be useful for estimating the annual effective dose status of Korean adults who consume foods containing ⁴⁰K and ¹³⁷Cs.

• 대한방사선기술학회지:방사선기술과학
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• 제41권4호
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• pp.351-360
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• 2018

In recent years, demand for examination of bone mineral density (BMD) is increasing in Korea according aging society. Therefore, it is required to develop an efficient management program that can increase the safety and reliability of Dual Energy X-ray Absorptiometry (DXA) that can be applied to the criteria of the World Health Organization. It is necessary to develop a management program that can design a program to improve the accuracy and precision of the results of the analysis and to improve the accuracy of diagnosis of osteoporosis by development a high quality DXA report. It is recommended to prepare the examination manuals and to establish procedures of standard operating including the program to prevent the pitfalls during the examination, the compatibility evaluation of the examination data, and the contents of the radiation safety. In addition, relevant regulations on the production of high-quality DXA reports are required and government and related agencies should introduce individual and facility recognition programs through DXA measurement and education programs and training. It is considered that efforts should be made to prepare high quality DXA report by guidelines on all aspects of BMD for preparation about aging society.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.354-358
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• 2016

Background: To find out the leak characteristic of research reactor 'HANARO' building in a typhoon condition Materials and Methods: MELCOR code which normally is used to simulate severe accident behavior in a nuclear power plant was used to simulate the leak rate of air and fission products from reactor hall after the shutdown of the ventilation system of HANARO reactor building. For the simulation, HANARO building was designed by MELCOR code and typhoon condition passed through Daejeon in 2012 was applied. Results and Discussion: It was found that the leak rate is $0.1%{\cdot}day^{-1}$ of air, $0.004%{\cdot}day^{-1}$ of noble gas and $3.7{\times}10^{-5}%{\cdot}day^{-1}$ of aerosol during typhoon passing. The air leak rate of $0.1%{\cdot}day^{-1}$ can be converted into $1.36m^3{\cdot}hr^{-1}$, but the design leak rate in HANARO safety analysis report was considered as $600m^3{\cdot}hr^{-1}$ under the condition of $20m{\cdot}sec^{-1}$ wind speed outside of the building by typhoon. Conclusion: Most of fission products during the maximum hypothesis accident at HANARO reactor will be contained in the reactor hall, so the direct radiation by remained fission products in the reactor hall will be the most important factor in designing emergency preparedness for HANARO reactor.

• Journal of Radiation Protection and Research
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• 제44권3호
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• pp.118-126
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• 2019

Background: Government conducts environmental radioactivity surveillance for verification purpose around nuclear facilities based on the Nuclear Safety Law and issues a surveillance report every year. This study aims to evaluate the short and the long-term fluctuation of radionuclides detected above MDC and their origins using concentration ratios between these radionuclides. Materials and Methods: Sample media for verification surveillance are air, rainwater, groundwater, soil, and milk for terrestrial samples, and seawater, marine sediment, fish, and seaweed for marine samples. Gamma-emitting radionuclides including $^{137}Cs$, $^{90}Sr$, Pu, $^3H$, and $^{14}C$ are evaluated in these samples. Results and Discussion: According to the result of the environmental radioactivity verification surveillance in the vicinity of nuclear power facilities in 2017, the anthropogenic radionuclides were not detected in most of the environmental samples except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples. Radioactivity concentration ratios between the anthropogenic radionuclides ($^{137}Cs/^{90}Sr$, $^{137}Cs/^{239+240}Pu$, $^{90}Sr/^{239+240}Pu$) were similar to those reported in the environmental samples, which were affected by the global fallout of the past nuclear weapon test, and Pu atomic ratios ($^{240}Pu/^{239}Pu$) in the terrestrial sample and marine sample showed significant differences due to the different input pathway and the Pu source. Radioactive iodine ($^{131}I$) was detected at the range of < $5.6-190mBq{\cdot}kg-fresh^{-1}$ in the gulfweed and sea trumpet collected from the area of Kori and Wolsong intake and discharge. A high level of $^3H$ was observed in the air (Sangbong: $0.688{\pm}0.841Bq{\cdot}m^{-3}$) and the precipitation (Meteorology Post: $199{\pm}126Bq{\cdot}L^{-1}$) samples of the Wolsong nuclear power plant (NPP). $^3H$ concentration in the precipitation and pine needle samples showed typical variation pattern with the distance and the wind direction from the stack due to the gaseous release of $^3H$ in Wolsong NPP. Conclusion: Except for the detection of a trace level of $^{137}Cs$, $^{90}Sr$, Pu, and $^{131}I$ in some samples, anthropogenic radionuclides were below MDC in most of the environmental samples. Overall, no unusual radionuclides and abnormal concentration were detected in the 2017's surveillance result for verification. This research will be available in the assessment of environment around nuclear facilities in the event of radioactive material release.

• Radiation Oncology Journal
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• 제28권1호
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• pp.50-56
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• 2010

목 적: 제 3기관에 의해 독립적으로 수행된 방사선 치료 빔의 흡수 선량을 외부 감사의 결과로 보고 한다. 이를 위해 쉽고 편리하게 설치 가능 한 고체 팬텀을 이용하여 흡수 선량을 측정하는 방법을 개발했다. 대상 및 방법: 2008년 12개 방사선 치료 시설에서 외부 감사 프로그램에 참여하였고 47개의 광자선과 전자선의 제 3기관에 의해 American Association of Physicists in Medicine (AAPM) task group (TG)-51 프로토콜을 사용하여 독립적으로 교정되었다. AAPM TG-51 프로토콜은 물에서의 측정을 권고 하고 있지만 팬텀으로 물은 바쁜 병원 상황에선 몇 가지 단점이 있다. 설치와 수송이 편리하고 재현성이 있는 고체 팬텀을 사용하였다. 광자선과 전자선에 대한 물과 고체 팬텀 사이의 선량 보정인자는 스케일링 방법과 실험적 측정에 의해 결정되었다. 결 과: 대부분의 빔은(74%) 제3기관의 프로토콜로 측정한 결과 2%의 편차 이내였다. 그러나 20개 중 2개의 광자선과 27개 중 3개의 전자선은 허용범위(3%)를 초과 하였다. 특히 그중 2개의 빔은 10% 이상의 편차를 보여주고 있다. 6 MV 초과의 고에너지 광자선은 보정인자가 없었다. 6 MV 광자선의 경우 고체 팬텀에서의 흡수선량은 물에서의 흡수 선량보다 0.4% 작게 나타났다. 전자선에 대한 보정인자도 결정되었는데 전자선의 에너지가 증가함에 따라 보정인자는 작아지는 경향을 보여준다. 고체팬텀을 사용한 TG-51 프로토콜의 측정 오차는 ${\pm}1.22%$로 나타났다. 결 론: 개발된 방법은 다기관 임상 연구의 인증 프로그램에 참여할 수 있는 외부 감사 기관 프로그램에 성공적으로 적용되었다. 이 선량측정은 선량을 측정하기 위한 시간을 줄이고 물을 설치할 때의 생길 수 있는 측정오차를 감소시킨다.

• Journal of Radiation Protection and Research
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• 제42권2호
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• pp.114-129
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• 2017

Background: The purpose of this paper is to confirm the event timings and the magnitude of fission product aerosol release from the Fukushima accident. Over a few hundreds of technical papers have been published on the environmental impact of Fukushima Daiichi accident since the accident occurred on March 11, 2011. However, most of the research used reverse or inverse method based on the monitoring of activities in the remote places and only few papers attempted to estimate the release of fission products from individual reactor core or from individual spent fuel pool. Severe accident analysis code can be used to estimate the radioactive release from which reactor core and from which radionuclide the peaks in monitoring points can be generated. Materials and Methods: The basic material used for this study are the initial core inventory obtained from the report JAEA-Data/Code 2012-018 and the given accident scenarios provided by Japanese Government or Tokyo Electric Power Company (TEPCO) in official reports. In this research a forward method using severe accident progression code is used as it might be useful for justifying the results of reverse or inverse method or vice versa. Results and Discussion: The release timing and amounts to the environment are estimated for volatile radioactive fission products such as noble gases, cesium, iodine, and tellurium up to 184 hours (about 7.7 days) after earthquake occurs. The in-plant fission product behaviors and release characteristics to environment are estimated using the severe accident progression analysis code, MELCOR, for Fukushima Daiichi accident. These results are compared with other research results which are summarized in UNSCEAR 2013 Report and other technical papers. Also it may provide the physically based arguments for justifying or suspecting the rationale for the scenarios provided in open literature. Conclusion: The estimated results by MELCOR code simulation of this study indicate that the release amount of volatile fission products to environment from Units 1, 2, and 3 cores is well within the range estimated by the reverse or inverse method, which are summarized in UNSCEAR 2013 report. But this does not necessarily mean that these two approaches are consistent.

• Journal of Radiation Protection and Research
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• 제23권3호
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• pp.149-157
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• 1998

개인 선량한도를 하향조정 하였을 경우 추가적으로 요구되는 방사선작업 자 수와 집단선량을 예측하기 위한 연구가 수행되었다. 연구대상은 한국원자력안전기술원에서 선택한 기관 모두를 포함하였고 해석기준의 선량한도는 ICRP Publ. 60. 및 BEIR V 보고서가 권고한 값으로 하였다. 해석자료로 사용된 데이터베이스는 원자력법에 의거 원자력발전사업 허가자와 비파괴검사 허가자가 한국방사성동위원소협회에 제출한 개인피폭선량 기록의 편집자료에 근거하였다. 연간 개인선량한도의 하향 설정에 따른 영향은 상관모델을 사용하여 계산하였다. 본 연구모델의 민감도는 종사자가 방사선작업환경 내에 있는 동안의 비생산성을 가정하여 분석하였다. 최상의 방사선작업환경조건에서도 종사자의 최저 비생산성 인자에 접근하는 것이 대단히 어렵기 때문에 최저 비생산성 가정은 보수적인 가정이라는 주장을 쉽게 변호할 수 있다는 것이 장점이다. 개인선량한도가 연평균 2cSv로 하향 조정되고 개인 작업자의 비생산성율이 0.1이라고 가정하면 1997년 동안 방사선시설에서 추가로 요구되는 방사선작업종사자수는 231명으로부터 269명으로 증가되고, 집단선량 man-cSv는 근사적으로 14%만큼 증가된다.