• Title/Summary/Keyword: 감마선 선원

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Study of the Radioactive Source Detection and the Visualization with the Stereo Radiation Detector (스테레오 기반 감마선원 탐지 및 가시화에 관한 연구)

  • Park, Gang-teak;Lee, Nam-ho;Cha, Han-ju
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2015.10a
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    • pp.1100-1102
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    • 2015
  • In the study, stereo-based of gamma-ray sources detector for the space including the gamma-ray source to scan in a raster scan method, and obtains a visible light image and the gamma-ray image. We went to retrieve and visualize the distance to source and the direction of the 3-dimension information from Stereo gamma-ray detectors. Configuration of the detector consisted of gamma-ray detecting sensor for gamma-ray Sources, pan-tilt for the scanning of the raster for detecting sources, and CCD camera for visible-light image. Implement a stereo structure of the device to measure the spatial distribution of source, the gamma-ray Detector and CCD camera for the stereo image acquisition was as each configuration 2. The gamma-ray detector and a visible light camera to revision the distribution of detection source, After performing each of the cameras of the stereo correction and shows the distribution of the gamma-ray Sources through 중첩 visible light image and the gamma-ray image. After Rectification process of Left and right image, we were derived visualization results of the stereo image.

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The Visualization and the Fast Detection of Gamma Radiation Source using Stereo Image Processing (영상처리기반 감마선원 거리탐지 고속화 및 가시화 연구)

  • Hwang, Young-Gwan;Lee, Nam-Ho
    • Journal of the Korea Institute of Information and Communication Engineering
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    • v.20 no.10
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    • pp.2001-2006
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    • 2016
  • The stereo radiation detection system detects the gamma source and acquires two dimensional left and right images for gamma source and visible objects using the detection result. And then the system measures the distance to the radiation source from the system in 3D space using stereo vision algorithm. In this paper, we implemented the fast detection algorithm for gamma source from the system in 3D space to reduce the detection time with image processing algorithms. Additionally, the system's performance is verified through experiments on gamma irradiation facilities. As a result, if the fast detection algorithm applied to the system, we can confirm that the detection system represents a 35% better performance than the conventional detection method that is full scanning to acquire the stereo image. We also have visualized a gamma source distribution through a 3D monitor using the stereo vision algorithm in order to provide the information of radiation spatial distribution to the user efficiently.

Development of High-Sensitivity Detection Sensor and Module for Spatial Distribution Measurement of Multi Gamma Sources (감마선원의 공간분포 가시화 및 3D모델링을 위한 운용환경 개발)

  • Song, Keun-Young;Lim, Ji-Seok;Choi, Jung-Huk;Yuk, Young-Ho;Hwang, Young-Gwan;Lee, Nam-Ho
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2017.10a
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    • pp.702-704
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    • 2017
  • In case of dismantling of nuclear power generation facility or radiation accident, the accurate information of gammaray source is essential for rapid decontamination. In order to more efficiently represent the position of the gamma ray to be removed, we create a spatial domain based on the real image. And we can perform decontamination of gamma-ray source more quickly by expressing the distribution of radiation source. The developed gamma ray imaging device overlaps with the visible image after gamma - ray detection and provides only two - dimensional image, but it does not show the distance information to the source. In this paper, we have developed a operation environment using the 3D visualization model for reporting effective decontamination operation.

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Development of High-Sensitivity Detection Sensor and Module for Spatial Distribution Measurement of Multi Gamma Sources (다종 감마선 공간분포 측정을 위한 고감도 검출센서 및 탐지모듈 개발)

  • Hwang, Young-Gwan;Lee, Nam-Ho
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2017.10a
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    • pp.705-707
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    • 2017
  • Stereo-based spatial radiation detection devices can obtain not only spatial distribution information about the radiation source but also distance information from the detection device to the source. And it provides more efficient information on the source than the existing radiation imaging device. In order to provide high-speed information on the spectrum and type of gamma-ray source, a high-sensitivity detection sensor with high sensitivity is required, and a technique capable of solving the saturation phenomenon at a high dose is needed. In this paper, we constructed a high sensitivity sensor for the measurement of multiple gamma - ray spatial distributions using improved function of detection module to solve saturation to high dose and conducted research to increase the scope of a single detector. The result of this paper improves the performance of gamma ray.

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Development of a simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector (HPGe 검출기를 사용한 감마분광분석계의 점검선원 개발)

  • Lee, Mo Sung
    • Journal of Radiation Protection and Research
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    • v.38 no.2
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    • pp.119-123
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    • 2013
  • A simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector was developed. The check source consists of radium-riched soil which was ground in size of less than 0.154mm and contained in air tight cylinderical vial, and provides photons with 12 distinct energies. The spectra of the check source were measured once a month during one year, analyzed the charactreictics of their peaks. When the gamma spectrometry system was in normal state, the areas and FWHMs of the gamma rays with more than 3% gamma emission rate in radium and its decay products was constant within standard deviation 2% and 3%, respectively, except 77 keV peak. And it was found that this check source can play a sufficient role to check the integrity of a gamma spectrometry system using 10 peaks in the range of 77 to 2202 keV.

Development of Neutron Induced Prompt γ-ray Spectroscopy System Using 252Cf (252Cf 선원을 이용한 즉발감마선 계측시스템 구성)

  • Park, Yong-Joon;Song, Byung-Chul;Jee, Kwang-Yong
    • Analytical Science and Technology
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    • v.16 no.1
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    • pp.12-24
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    • 2003
  • For the design and set-up of neutron induced prompt ${\gamma}$-ray spectroscopy system using $^{252}Cf$ neutron source, the effects of shielding and moderator materials have been examined. The $^{252}Cf$ source being used for TLD badge calibration in Korea Atomic Energy Research Institute was utilized for this preliminary experiment. The ${\gamma}$-ray background and prompt ${\gamma}$-ray spectrum of the sample containing Cl were measured using HPGe (GMX 60% relative efficiency) located at the inside of the system connected to notebook PC at the outside of the system (about 20 meter distance). The background activities of neutron and ${\gamma}$-rays were measured with neutron survey meter as well as ${\gamma}$-ray survey meters, respectively and the system was designed to minimize the activities. Prompt ${\gamma}$-ray spectrum was measured using ${\gamma}$-${\gamma}$ coincident system for reduce the background and the continuum spectrum. The optimum system was designed and set up using the experimental data obtained.

Comparison of the Correction Methods for Gamma Ray Attenuation in the Radioactive Waste Drum Assay (방사성폐기물드럼 핵종분석에서 감마선 감쇠보정 방법들의 비교 평가)

  • Ji Young-Yong;Ryu Young-Gerl;Kwak Kyoung-Kil;Kang Duck-Won;Kim Ki-Hong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.3
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    • pp.275-284
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    • 2006
  • In the measurement of gamma rays emitted from the nuclide in the radioactive waste drum, to analyze the nuclide concentration accurately, it is necessary to use the proper calibration standards and to correct for the attenuation of the gamma rays. Two drums having a different density were used to analyze the nuclide concentration inside the drum in this study. After carrying out the system calibration, we measured the gamma rays emitted from the standard source inside the model drum with changing the distance between the drum and the detector. The measured values were corrected with the three kinds of gamma attenuation correction methode, as a results, the error was less than 10 % in the low density drum and less than 25 % in the high density drum. The measured activity in the short distance was more accruable than in the long distance. The transmission correction for the mass attenuation showed good results(very Low error) compared to the mean density and the differential peak correction method.

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The Study Image Aquisition System for Radiation Source Using the Stereo Gamma-ray Detector (스테레오 감마선 탐지장치를 이용한 감마선원 분포측정 시스템에 관한 연구)

  • Hwang, Young-Gwan;Lee, Nam-Ho;Lee, Seung-Min
    • Journal of the Institute of Electronics and Information Engineers
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    • v.52 no.4
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    • pp.197-203
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    • 2015
  • Nuclear power plant has increased continuously for power production in all over the world and the interest about nuclear accident and the dismantling of aging nuclear power plant has been a growing. The leaked radioactive source that is generated by radiation accidents must detect and remove to minimized the damage as soon as possible. Gamma-ray detection system that have been developed until now cannot provide the precise position of radioactive sources because they detect and imaging the position of radiation sources in just two dimensions. In this paper, stereo gamma ray detection system has developed and the algorithm for calculation of the distance has implemented to be able to measure the distribution of the leakage gamma ray source for the system. Stereo camera calibration for distance detection was conducted with the correction pattern and LED light and we carried out performance test of the system for the LED light source and a gamma ray source. In both experiments the results of the performance test, it was confirmed to have a 5% error. The results of this paper is used as a material for the development of gamma-ray imaging device.

The Study for Improved Efficiency of the Detection of Radiation Sources Distribution using Image Processing (영상처리기반 감마선 분포탐지 효율 개선에 관한 연구)

  • Hwang, Young-gwan;Lee, Nam-ho;Kim, Jong-yeol;Jeong, Sang-hun
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2016.05a
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    • pp.780-781
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    • 2016
  • The stereo radiation detection system detects gamma ray source and measures the two dimensional distribution image based on the detection result. Then the system is implemented to measure the distance to the radiation source from the system in 3D space using stereo vision algorithm. In this paper, we reduced the time for a gamma-ray scan space detection through image processing algorithms. In addition, it combines radiation and visible light images. Then we conducted a study for improving the distribution of gamma-ray detection efficiency through the stereo calibration using a 3D visualization. As a result, we obtain an improved detection time by more than 30% and have acquired a visible image with a 3D monitor.

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Manufacture of a Gamma-ray Source using the Neutron Activation and Determination of a HPGe Detector Efficiency (중성자 방사화법을 이용한 감마선원 제조 및 HPGe 검출기 효율 결정)

  • Seo, Bum-Kyoung;Lee, Kil-Yong;Yoon, Yoon-Yeol;Lee, Kune-Woo
    • Journal of Radiation Protection and Research
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    • v.29 no.1
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    • pp.17-23
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    • 2004
  • In order to save time and money needed in the purchase commonly used gamma-ray standard sources, a new radioactive standard source was manufactured by the neutron activation of some regent in the research reactor HANARO. The source was manufactured with an aqueous solution by mixing and dissolving the irradiated reagents. The manufactured source was compared with a commercial standard source. It was confirmed that it could be used as an efficiency calibration source. Also, in order to compare the variation of efficiency due to the volume difference for various containers used in radioactivity assay, the efficiency variation as a function of sample volume was investigated.