• 제목/요약/키워드: Leakage Radiation

검색결과 205건 처리시간 0.024초

30 MeV 사이클로트론 시설 위험성 평가 (Risk Assessment of 30 MeV Cyclotron Facilities)

  • 정교성;김종일;이진우
    • 방사선산업학회지
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    • 제11권1호
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    • pp.39-45
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    • 2017
  • A cyclotron is a kind of particle accelerator that produces a beam of charged particles for the production of medical, industrial, and research radioisotopes. More than 30 cyclotrons are operated in Korea to produce $^{18}F$, an FDG synthesis at hospitals. A 30-MeV cyclotron was installed at ARTI (Advanced Radiation Technology Institute, KAERI) mainly for research regarding isotope production. In this study, we analyze and estimate the items of risk such as the problems in the main components of the cyclotron, the loss of radioactive materials, the leakage of coolant, and the malfunction of utilities, fires and earthquakes. To estimate the occurrence frequency in an accident risk assessment, five levels, i.e., Almost certain, Likely, Possible, Unlikely, and Rare, are applied. The accident consequence level is classified under four grades based on the annual permissible dose for radiation workers and the public in the nuclear safety law. The analysis of the accident effect is focused on the radioactive contamination caused by radioisotope leakage and radioactive material leakage of a ventilation filter due to a fire. To analyze the risks, Occupation Safety and Health Acts is applied. In addition, action plans against an accident were prepared after a deep discussion among relevant researchers. In this acts, we will search for hazard and introduce the risk assessment for the research 30-MeV cyclotron facilities of ARTI.

새로 개발된 Multi-leaf Collimator의 임상 유효성 및 방사선 안전성에 관한 연구 (The Clinical effectiveness and the radiation safety of newly developed Multileaf Collimator)

  • 이병용;김종훈;안승도;김미화;장혜숙
    • 대한의용생체공학회:학술대회논문집
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    • 대한의용생체공학회 1996년도 춘계학술대회
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    • pp.157-160
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    • 1996
  • We have developed the prototype Multi-leaf Collimator(MLC) for medical linear acclerator. In this study, we have examined the clinical effectiveness of our newly developed MLC by analysing treatment pattern of radiation therapy and studied the radiation safety by measuring the transmitted radiation and the leakage radiation. Over 81% patients can be treated with new MLC(20 pairs of leaves) and 98% with 30 pairs of leafed-MLC, while 95% with commercial MLC. New MLC showed superior properties of radiation leakage and transmission to commercially available MLC.

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완전차폐 및 이온조절형 연X선식 정전기제거장치의 개발 (Development of Radiation Free Soft X-Ray Ionizer with Ion Control)

  • 정필훈;이동훈
    • 한국안전학회지
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    • 제31권5호
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    • pp.22-27
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    • 2016
  • The Electrostatic Charge Prevention Technology is a core factor that highly influences the yield of Ultra High Resolution Flat Panel Display and high-integrated semiconductor manufacturing processes. The corona or x-ray ionizations are commonly used in order to eliminate static charges during manufacturing processes. To develop such a revolutionary x-ray ionizer that is free of x-ray radiation and has function to control the volume of ion formation simultaneously is a goal of this research and it absolutely overcomes the current risks of x-ray ionization. Under the International Commission on Radiological Protection, it must have a leakage radiation level that should be lower than a recommended level that is $1{\mu}Sv/hour$. In this research, the new generation of x-ray ionizer can easily control both the volume of ion formation and the leakage radiation level at the same time. In the research, the test constraints were set and the descriptions are as below; First, In order not to leak x-ray radiation while testing, the shielding box was fully installed around the test equipment area. Second, Implement the metallic Ring Electrode along a tube window and applied zero to ${\pm}8kV$ with respect to manage the positive and negative ions formation. Lastly, the ion duty ratio was able to be controlled in different test set-ups along with a free x-ray leakage through the metallic Ring Electrode. In the result of experiment, the maximum x-ray radiation leakage was $0.2{\mu}Sv/h$. These outcome is lower than the ICRP 103 recommended value, which is $1{\mu}Sv/h$. When applying voltage to the metallic ring electrode, the positive decay time was 2.18s at the distance of 300 mm and its slope was 0.272. In addition, the negative decay time was 2.1s at the distance of 300 mm and its slope was 0.262. At the distance of 200 mm, the positive decay time was 2.29s and its slope was 0.286. The negative decay time was 2.35s and its slope was 0.293. At the distance of 100 mm, the positive decay time was 2.71s and its slope was 0.338. The negative decay time was 3.07s and its slope was 0.383. According to these research, the observation was shown that these new concept of ionizer is able to minimize the leakage radiation level and to control the positive and negative ion duty ratio while ionization.

Implementation of a Radiation-hardened I-gate n-MOSFET and Analysis of its TID(Total Ionizing Dose) Effects

  • Lee, Min-Woong;Lee, Nam-Ho;Jeong, Sang-Hun;Kim, Sung-Mi;Cho, Seong-Ik
    • Journal of Electrical Engineering and Technology
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    • 제12권4호
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    • pp.1619-1626
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    • 2017
  • Electronic components that are used in high-level radiation environment require a semiconductor device having a radiation-hardened characteristic. In this paper, we proposed a radiation-hardened I-gate n-MOSFET (n-type Metal Oxide Semiconductors Field Effect Transistors) using a layout modification technique only. The proposed I-gate n-MOSFET structure is modified as an I-shaped gate poly in order to mitigate a radiation-induced leakage current in the standard n-MOSFET structure. For verification of its radiation-hardened characteristic, the M&S (Modeling and Simulation) of the 3D (3-Dimension) structure is performed by TCAD (Technology Computer Aided Design) tool. In addition, we carried out an evaluation test using a $Co^{60}$ gamma-ray source of 10kGy(Si)/h. As a result, we have confirmed the radiation-hardened level up to a total ionizing dose of 20kGy(Si).

Radiation Safety Exploration Using Radio-photoluminescence Dosimeter for Crookes Tubes in Junior and Senior High School in Japan

  • Akiyoshi, Masafumi;Do, Duy Khiem;Yamaguchi, Ichiro;Kakefu, Tomohisa;Miyakawa, Toshiharu
    • Journal of Radiation Protection and Research
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    • 제46권3호
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    • pp.106-111
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    • 2021
  • Background: Crookes tube is utilized in junior high and high schools in Japan to study the character of electrons and current, and not for radiological education. There is no official guideline or regulation for these radiation source to the public. Therefore, most teachers have no information about the leakage of X-rays from Crookes tube. The peak energy of X-rays is approximately 20 keV, and it is impossible to measure using conventional survey meters. Materials and Methods: Each leakage dose of low energy X-rays from 38 Crookes tube in the education field, such as junior and senior high schools in Japan, was explored by the teachers in the school using radio-photoluminescence (RPL) dosimeters. Before and after the measurements, the dosimeters were sent by postal mails. Results and Discussion: At the exploration in this study, it was estimated that the 70 ㎛ dose equivalent, Hp(0.07) of X-rays from 31 Crookes tubes were smaller than 100 µSv in 10 minutes, at the distance of 1 m, where the Crookes tube was usually observed. However, the highest dose was estimated as 0.69 mSv by an equipment with the full power. Furthermore, one Crookes tube exhibited 0.62 mSv with minimum output power of the induction coil. This relatively large dose was reduced by the shorter distance of discharge electrodes of the induction coil. Conclusion: The leakage dose of low energy X-rays from 38 Crookes tube was explored using RPL dosimeters. It was estimated that the Hp(0.07) of X-rays from 31 Crookes tubes were smaller than 100 µSv in 10 minutes at the distance of 1 m, while some equipment radiated a higher dose. With this study, the provisional guideline for the safety operation of Crookes tube is established.

미생물의 세포생리에 미치는 전이방사선의 영향에 관한 연구 (제 5 ) "-의 과성에 대한 $\gamma$-의 영향에 대하여" (Studies on the cellular metabolism in microorganisms as influenced by gamma-irradiation.(V) "On the membrane permeability changes and leakage of celluar constituents of irradiated yeast cell")

  • 김종협;전세열;김희자
    • 미생물학회지
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    • 제6권2호
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    • pp.54-62
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    • 1968
  • The effect of gamma-ray on yeast cells Sacch. cerevisiae, and the leakage of cellular constituents such as carbohydrates, ribose, amino acids, inorganic phosphates and organic phosphates have been studied. The samples of yeast cells washed throughly and starved intensively, radiation effects were compared with those of control (un-starved), the irradiation dose rates are in the range from 24 Kr. up. to 480, Kr. The loss of 260m$\mu$. absorbing material, are also observed. Mechanisms of membrane damage by gamma-irradiation are discussed corelating to permeability changes and loss of substances, then active and passive transport process are also under considerations in discussion. The experimental results are as follows, 1. Carbohydrates of yeast cell leak out by gamma-irradiation, and amounts of loss increase proportionally as the increasing of radiation dose, curve of carbohydrates loss in starved cells is parallel with those of non-starved cells. 2. Ribose leak out less than that of carbohydrate from irradiated cell, the dose response curve of loss is straight and proportional to the increasing of radiation doses, slope of the curve is much lower than of carbohydrates. 3. Amino acids also leak out and the curve of losses to radiation is not proportional, it is revealed that there are little losses from yeast at lower doses of irradiation. 4. The losses of inorganic phosphates increase unproportionally to the increasing of irradiation doses, there are little leakage at the lower doses of irradiation. The losses of organic phosphates increase proportionally to the increasing of irradiation doses, and the amount of losses are much more than that of inorganic phosphate at lower doses of irradiation. 5. Leakage from irradiated yeast cells was shown to be due to passive transport process not an energy requiring process of ion transport. 6. Loss of 260 m$\mu$. absorbing material is little more than that of control yeast by the gamma-irradiation dose of 120K.r. and 240K.r.

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핀홀 스테레오 비전 센서의 공간 스캔을 통한 방사선의 영상화 시뮬레이션 (Simulation of Radiation Imaging based on the Scanning of Pin-hole Stereo Vision Sensors)

  • 박순용;백승해;최창원
    • 한국정보통신학회논문지
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    • 제18권7호
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    • pp.1671-1680
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    • 2014
  • 원자력 발전소에서 예기치 못한 사고가 발생하거나 발전소를 해체하는 작업을 수행하는 과정에서는 방사선 물질의 유출에 대한 우려가 항상 존재한다. 유출된 방사선 물질을 제거하기위해서는 방사선의 분포에 대한 정확한 정보를 획득할 수 있는 기술이 필요하다. 그러나 방사선 물질의 직접적 취급은 매우 제한적이기 때문에 방사선과 관련된 기술의 개발은 미리 시뮬레이션을 통하여 그 가능성을 검토하여야 한다. 본 논문에서는 방사선 물질의 분포에 대한 3차원 정보를 획득할 수 있는 방사선 영상화 기술을 시뮬레이션하였다. 두 개의 가상의 1차원 방사선 센서를 이용하여 스테레오 방사선 영상을 획득하고, 스테레오 시차를 이용하여 가상의 방사선 물질에 대한 3차원 거리 정보를 획득하였다. 점과 면으로 구성된 가상의 방사선 물질에 대하여 스테레오 방사선 영상 및 3차원 정보의 획득이 가능함을 시뮬레이션하였다.

산업용 EMS를 고려한 누설전류 센싱 컨트롤러의 개발 (Development of Leakage Current Sensing Controller in Consideration of Industrial EMS)

  • 박성원;노인배;김상동;박지호;김동완
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2009년도 춘계학술대회 논문집 전기설비전문위원
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    • pp.70-71
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    • 2009
  • In recent years, a importance of EMS(Electromagnetic Susceptibility) is increased with the spread of a communication device significantly. The compatibility of EMS is evaluated by conduction and radiation of EMI(Electromagnetic Interference). In this paper, a leakage current sensing controller which is considered of industrial EMS is developed. The developed system is consisted of power module, sensing module of leakage current, processer module, display module and communication module. The developed system is evaluated the compatibility of EMS by conduction and radiation of EMI. In evaluation results, the developed system is compatible to the standard of industrial EMS.

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CMOS 0.18um 공정 단위소자의 방사선 영향 분석 (Analysis of Radiation Effects in CMOS 0.18um Process Unit Devices)

  • 정상훈;이남호;이민웅;조성익
    • 전기학회논문지
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    • 제66권3호
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    • pp.540-544
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    • 2017
  • In this study, we analyzed the effects of TID(Total Ionizing Dese) and TREE(Transient Radiation Effects on Electronics) on nMOSFET and pMOSFET fabricated by 0.18um CMOS process. The size of nMOSFET and pMOSFET is 100um/1um(W/L). The TID test was conducted up to 1 Mrad(Si) with a gamma-ray(Co-60). During the TID test, the nMOSFET generated leakage current proportional to the applied dose, but that of the pMOSFET was remained in a steady state. The TREE test was conducted at TEST LINAC in Pohang Accelerator Laboratory with a maximum dose-rate of $3.16{\times}10^8rad(si)/s$. In that test nMOESFET generated a large amount of photocurrent at a maximum of $3.16{\times}10^8rad(si)/s$. Whereas, pMOSFETs showed high TREE immunity with a little amount of photocurrent at the same dose rate. Based on the results of this experiment, we will progress the research of the radiation hardening for CMOS unit devices.

Feasibility Study of Beta Detector for Small Leak Detection inside the Reactor Containment

  • Jang, JaeYeong;Schaarschmidt, Thomas;Kim, Yong Kyun
    • Journal of Radiation Protection and Research
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    • 제43권4호
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    • pp.154-159
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    • 2018
  • Background: To prevent small leakage accidents, a real-time and direct detection system for small leaks with a detection limit below that of existing systems, e.g. $0.5gpm{\cdot}hr^{-1}$, is required. In this study, a small-size beta detector, which can be installed inside the reactor containment (CT) building and detect small leaks directly, was suggested and its feasibility was evaluated using MCNPX simulation. Materials and Methods: A target nuclide was selected through analysis of radiation from radionuclides in the reactor coolant system (RCS) and the spectrum was obtained via a silicon detector simulated in MCNPX. A window was designed to reduce the background signal caused by other nuclides. The sensitivity of the detector was also estimated, and its shielding designed for installation inside the reactor CT. Results and Discussion: The beta and gamma spectrum of the silicon detector showed a negligible gamma signal but it also contained an undesired peak at 0.22 MeV due to other nuclides, not the $^{16}N$ target nuclide. Window to remove the peak was derived as 0.4 mm for beryllium. The sensitivity of silicon beta detector with a beryllium window of 1.7 mm thickness was derived as $5.172{\times}10^{-6}{\mu}Ci{\cdot}cc^{-1}$. In addition, the specification of the shielding was evaluated through simulations, and the results showed that the integrity of the silicon detector can be maintained with lead shielding of 3 cm (<15 kg). This is a very small amount compared to the specifications of the lead shielding (600 kg) required for installation of $^{16}N$ gamma detector in inside reactor CT, it was determined that beta detector would have a distinct advantage in terms of miniaturization. Conclusion: The feasibility of the beta detector was evaluated for installation inside the reactor CT to detect small leaks below $0.5gpm{\cdot}hr^{-1}$. In future, the design will be optimized on specific data.