• 제목/요약/키워드: gamma-ray detector

검색결과 263건 처리시간 0.019초

감마선 검출용 $HgI_2$ 소자 제작 및 특성 평가 (Fabrication and Test of a $HgI_2$ Gamma Ray Detector)

  • 최명진;이홍규;강영일;임호진;최승기
    • Journal of Radiation Protection and Research
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    • 제16권2호
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    • pp.1-6
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    • 1991
  • 상온에서 사용할 수 있는 감마선 검출 소자로서 $HgI_2$ 소자의 응용성을 판단하기 위하여 기상 성장법으로 $HgI_2$ 단결정을 성장시켰고 이를 이용하여 검출 소자를 제작한 후 감마선 검출 특성을 조사하였다 성장된 단결정의 비저항과 전하 운반자 포획 밀도는 상온에서 각각 $10^{11}{\Omega}\;cm$$1.8{\times}10^{14}/cm^3$였으며 단결정의 Photoluminescence를 측정한 결과 성장된 $HgI_2$ 단결정의 밴드갭의 온도계수는 20K부터 77K에서 $-1.53{\times}10^{-4}eV/K$였다. 감마선 검출실험 결과 제작된 $HgI_2$ 검출 소자는 상온에서 우수한 계수 특성과 시간에 대한 선형적 축적 계수 특성을 나타내었으나 온도변화에 따라 계수의 특성의 변화는 심하였다.

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Effects of element composition in soil samples on the efficiencies of gamma energy peaks evaluated by the MCNP5 code

  • Ba, Vu Ngoc;Thien, Bui Ngoc;Loan, Truong Thi Hong
    • Nuclear Engineering and Technology
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    • 제53권1호
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    • pp.337-343
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    • 2021
  • In this work, self-absorption correction factor related to the variation of the composition and the density of soil samples were evaluated using the p-type HPGe detector. The validated MCNP5 simulation model of this detector was used to evaluate its Full Energy Peak Efficiency (FEPE) under the variation of the composition and the density of the analysed samples. The results indicates that FEPE calculation of low gamma ray is affected by the composition and the density of soil samples. The self-absorption correction factors for different gamma-ray energies which was fitted as a function of FEPEs via density and energy and fitting parameters as polynomial function for the logarithm neper of gamma ray energy help to calculate quickly the detection efficiency of detector. Factor Analysis for the influence of the element composition in analysed samples on the FEPE indicates the FEPE distribution changes from non-metal to metal groups when the gamma ray energy increases from 92 keV to 238 keV. At energies above 238 keV, the FEPE primarily depends only on the metal elements and is significantly affected by aluminium and silicon composition in soil samples.

${\gamma}$-선 분광법을 이용한 한국산 방사성 원광내의 Uranium Thorium 함유량 측정 (Determination of % Contents of Uranium and Thorium in Natural Radioactive Ores by ${\gamma}$-ray Spectrometry)

  • 조성원;정문규;유건중;홍치유
    • Nuclear Engineering and Technology
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    • 제2권4호
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    • pp.273-278
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    • 1970
  • 국내에서 채광한 자연방사능광물의 분석의뢰를 계기로 이에 관심을 갖고 Uranium와Thorium 의 함유량을 원광으로부터 비파괴적이고 간단한 ${\gamma}$-선 분광법으로 측정 분석하여 보았다. Ge(Li) 측정기를 ${\gamma}$-선 분광에 이용한 결과는 재래식방법에 비하여 분석정도를 훨씬 높일 수 있었으며, 자연방사능측정법과 원자로중성자로 조사시킨 activation법으로 Uranium와 Thorium의 함유량을 분석하였던바 하나의 시료(인천에서 채광)에서는 약 0.5%의 Uranium, 또 다른 시료에서는 2%의 Th와 0.1%의 U이 포함되어 있음이 확인되었다. 우리가 처음 시도한 이 분석법은 경제적이고 간편.신속하게 분석할수 있어 핵연료물질조사에 널러 이용할 수 있음을 입증한다.

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Cd$_{80}$ Zn$_{20}$Te를 사용한 MIM 구조의 감마선 탐지 소자 제작 및 탐지 특성에 관한 연구 (A Study on the Fabrication and Detection of Cd$_{80}$ Zn$_{20}$Te Gamma-ray detector with MIM Structure)

  • 최명진;왕진석
    • 전자공학회논문지D
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    • 제34D권4호
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    • pp.47-53
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    • 1997
  • We fabricated gamma radiation detector using high resistive p-Cd$_{80}$Zn$_{20}$Te grown by high pressure bridgman method and forming au thin film electrode by chemically electroless deposition method. The device of Au/Cd$_{80}$Zn$_{20}$Te/Au is a typical MIM structure. The characteristic of current-voltage showed good linearity to 3kV/cm but it depend on the square of electric field over 3kV/cm. As the results of rutherford backscattering spectroscope(RBS) and auger spectroscope on the Au/Cd$_{80}$Zn$_{20}$Te, Au penetrated to the surface of Cd$_{80}$Zn$_{20}$Te detector absorbed slightly high energy radiation like a few hundred keV and showed good performance to detect low energy gamma ray.mma ray.

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SENSITIVITY ANALYSIS TO EVALUATE THE TRANSPORT PROPERTIES OF CdZnTe DETECTORS USING ALPHA PARTICLES AND LOW-ENERGY GAMMA-RAYS

  • Kim, Kyung-O;Ahn, Woo-Sang;Kwon, Tae-Je;Kim, Soon-Young;Kim, Jong-Kyung;Ha, Jang-Ho
    • Nuclear Engineering and Technology
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    • 제43권6호
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    • pp.567-572
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    • 2011
  • A sensitivity analysis of the methods used to evaluate the transport properties of a CdZnTe detector was performed using two different radiations (${\alpha}$ particle and gamma-ray) emitted from an $^{241}Am$ source. The mobility-lifetime products of the electron-hole pair in a planar CZT detector ($5{\times}5{\times}2\;mm^3$) were determined by fitting the peak position as a function of biased voltage data to the Hecht equation. To verify the accuracy of these products derived from ${\alpha}$ particles and low-energy gamma-rays, an energy spectrum considering the transport property of the CZT detector was simulated through a combination of the deposited energy and the charge collection efficiency at a specific position. It was found that the shaping time of the amplifier module significantly affects the determination of the (${\mu}{\tau}$) products; the ${\alpha}$ particle method was stabilized with an increase in the shaping time and was less sensitive to this change compared to when the gamma-ray method was used. In the case of the simulated energy spectrum with transport properties evaluated by the ${\alpha}$ particle method, the peak position and tail were slightly different from the measured result, whereas the energy spectrum derived from the low-energy gamma-ray was in good agreement with the experimental results. From these results, it was confirmed that low-energy gamma-rays are more useful when seeking to obtain the transport properties of carriers than ${\alpha}$ particles because the methods that use gamma-rays are less influenced by the surface condition of the CZT detector. Furthermore, the analysis system employed in this study, which was configured by a combination of Monte Carlo simulation and the Hecht model, is expected to be highly applicable to the study of the characteristics of CZT detectors.

방사성 오염도 측정을 위한 광섬유 검출기 제작 (Fabrication of Fiber-optics Detector for Measuring Radioactive Waste)

  • 김정호;주관식
    • 전기전자학회논문지
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    • 제19권3호
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    • pp.282-287
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    • 2015
  • 본 연구에서는 연구에서는 Ce:GAGG 섬광체, 광섬유 그리고 광전자증배관을 이용하여 광섬유 검출기를 제작하였다. 섬광체의 단결정 크기는 MCNPX 코드를 이용하여 섬광체 깊이에 따른 감마선 계수효율을 전산모사하여 $3{\times}3{\times}20mm^3$로 설정하였다. 제작된 검출기는 표준 감마선원인 $^{137}Cs$$^{133}Ba$을 이용하여 세기의 따른 선형성 평가와 거리 변화에 따른 계수량 변화 측정을 하였다. 그 결과 추세선식 R-square 값이 0.99741로 매우 좋은 응답선형성을 보였고, 거리에 따른 검출 특성 또한 MCNPX값과 비교하였을 때 2% 이하로 좋은 검출특성을 보였다. 또한 단일선원과 혼합선원에서의 감마선 에너지 분광 결과 $^{137}Cs$은 662keV에서 그리고 $^{133}Ba$은 356keV에서 감마선 에너지 피크를 확인하였다. 광섬유 검출기를 사용한다면 작업자의 작업시간과 피폭을 줄여줄 것으로 보인다.

100-MeV 양성자 빔을 이용하여 169Tm(p,3n)167Yb 반응에 의해 생성된 167Yb 방사성동위원소에서 방출되는 감마선 스펙트럼 비교 연구 (A Comparative Study of Branching Ratio of 167Yb Radioactive Isotope from Gamma-ray Spectrum Produced by 169Tm(p,3n)167Yb Reaction with 100-MeV Proton Beam)

  • 이삼열
    • 한국방사선학회논문지
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    • 제16권7호
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    • pp.953-960
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    • 2022
  • 양성자과학연구단의 100-MeV 양성자선형가속기의 양성자를 사용하여 천연 169Tm과 핵반응을 일으켜 167Yb 방사성동위원소를 생성하였다. 생성된 동위원소는 17.5분의 반감기를 가지며 167Tm로 붕괴한다. 이때 발생하는 감마선을 HPGe 검출시스템을 사용하여 측정하였다. 검출기의 에너지 교정 및 검출기의 효율 측정은 표준선원을 사용하여 결정하였다. 기존에 알려진 Table of Isotopes의 주요 감마선 에너지는 모두 측정되었다. 한편, 현재까지 알려진 발생되는 감마선의 강도에 대한 정보는 매우 부정확한 상황이다. 따라서 본 연구를 통하여 주요 감마선에 대한 붕괴 강도를 정확하게 측정하였다. 전체적으로 기존에 알려져 있던 결과들과 상이한 차이를 보였으며 특히 113.3 및 106.2 keV 감마선 같은 주 붕괴 감마선의 강도들이 과대평가 되었다는 사실을 알게 되었고 62.9, 116.7 및 143.56 keV의 감마선 들은 과소평가 된 감마선들임을 알게 되었다. 본 연구의 결과는 핵융합 연구, 천체 물리학 및 핵물리 분야에 있어서 중요한 정보가 될 것으로 생각된다.

Detection of voluminous gamma-ray source with a collimation beam geometry and comparison with peak efficiency calculations of EXVol

  • Kang, M.Y.;Sun, G.M.;Choi, H.D.
    • Nuclear Engineering and Technology
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    • 제52권11호
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    • pp.2601-2606
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    • 2020
  • In this study, we expanded the performance of the existing EXVol code and performed empirical experiments and calculations. A high-resolution gamma spectroscopy system was constructed, and a standard point source and a standard volume source were measured with an HPGe detector with 43.1% relative efficiency. EXVol was verified by quantitative comparison of the detection efficiencies determined by measurements and calculations. To introduce the concept of the detector scanning that occurs in the actual measurement into the EXVol code, a collimator was placed between the source and detector. The detection efficiency was determined in the asymmetric arrangement of the source and detector with a collimator. A collimator made of lead with a diameter of 15 mm and a thickness of 50 mm was installed between the source and the detector to determine the detection efficiency at a specific location. The calculation result was contour plotted so that the distribution of detection efficiency could be visually confirmed. The relative deviation between the measurements and calculations for the coaxial and asymmetric structures was 10%, and that for the collimation structure was 20%. The results of this study can be applied to research using γ-ray measurements.

감마선 분포 측정을 위한 섬광필름 기반의 감마 영상 검출기 제작 및 성능평가 (Fabrication and Performance Evaluation of a Scintillating Film-based Gamma Imaging Detector to Measure Gamma-ray Distribution)

  • 신상훈;유욱재;장경원;조승현;이봉수
    • 센서학회지
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    • 제24권3호
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    • pp.202-207
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    • 2015
  • As a feasibility study on development of a gamma imaging probe, we developed a scintillating film-based gamma imaging detector that can obtain scintillation images with information of gamma-ray distribution. The scintillating film-based gamma imaging detector was composed of a sensing probe, an image intensifier, and a beam profiler. To detect and transmit scintillation image, the sensing probe was fabricated by coupling a scintillating film, a fiber-optic image conduit, and a fiber-optic taper, consecutively. First, the optical images of USAF 1951 resolution target were obtained and then, modulation transfer function values were calculated to test the image quality of the sensing probe. Second, we measured the scintillation images according to the activity of the 137Cs and the distance between the surface of 137Cs and the distal-end of sensing probe. Finally, the intensities of scintillating light as functions of the activity and the distance were evaluated from the region of interest in the scintillation image. From the results of this study, it is expected that a fiber-optic gamma imaging detector can be developed to detect gamma-rays emitted from radiopharmaceuticals during radioimmunoguided surgery.

Characterization of a CLYC Detector and Validation of the Monte Carlo Simulation by Measurement Experiments

  • Kim, Hyun Suk;Smith, Martin B.;Koslowsky, Martin R.;Kwak, Sung-Woo;Ye, Sung-Joon;Kim, Geehyun
    • Journal of Radiation Protection and Research
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    • 제42권1호
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    • pp.48-55
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    • 2017
  • Background: Simultaneous detection of neutrons and gamma rays have become much more practicable, by taking advantage of good gamma-ray discrimination properties using pulse shape discrimination (PSD) technique. Recently, we introduced a commercial CLYC system in Korea, and performed an initial characterization and simulation studies for the CLYC detector system to provide references for the future implementation of the dual-mode scintillator system in various studies and applications. Materials and Methods: We evaluated a CLYC detector with 95% $^6Li$ enrichment using various gamma-ray sources and a $^{252}Cf$ neutron source, with validation of our Monte Carlo simulation results via measurement experiments. Absolute full-energy peak efficiency values were calculated for gamma-ray sources and neutron source using MCNP6 and compared with measurement experiments of the calibration sources. In addition, behavioral characteristics of neutrons were validated by comparing simulations and experiments on neutron moderation with various polyethylene (PE) moderator thicknesses. Results and Discussion: Both results showed good agreements in overall characteristics of the gamma and neutron detection efficiencies, with consistent ~20% discrepancy. Furthermore, moderation of neutrons emitted from $^{252}Cf$ showed similarities between the simulation and the experiment, in terms of their relative ratios depending on the thickness of the PE moderator. Conclusion: A CLYC detector system was characterized for its energy resolution and detection efficiency, and Monte Carlo simulations on the detector system was validated experimentally. Validation of the simulation results in overall trend of the CLYC detector behavior will provide the fundamental basis and validity of follow-up Monte Carlo simulation studies for the development of our dual-particle imager using a rotational modulation collimator.