• Title/Summary/Keyword: 방사선 검출기

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The Study of CsI(Tl) Scintillation Detector Design and Signal Processing for the Measurement of the Radiation Distribution (방사선 분포측정용 CsI(Tl) 검출기 설계 및 신호처리에 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.778-779
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    • 2016
  • In This paper, We designed the scintillation detector for measuring radiation signals in units of pixels for a radiation source that is distributed in the space. And we carried out a study to design a radiation imaging by the module for obtaining the detection signal. For measuring radiation distribution we configure a radiation detector combining CsI(Tl) scintillator and a photodiode. In addition, its performance was verified via gamma irradiation test.

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Development of Prototype Electronic Dosimeter using the Silicon PIN Diode Detector (실리콘 PIN 다이오드 검출기를 이용한 전자선량계 개발)

  • Lee, B.J.;Kim, B.H.;Chang, S.Y.;Kim, J.S.
    • Journal of Radiation Protection and Research
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    • v.25 no.4
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    • pp.197-205
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    • 2000
  • A prototype electronic dosimeter(PED) adopting a silicon PIN diode detector as a radiation detector has been developed, manufactured and test-evaluated. A radiation signal processing circuit has been electronically tested and then the radiation detection characteristics of this PED has been performance-tested by using a reference photon radiation field. As a result in a electronic performance test, radiation signals from a detector were well observed in the signal processing circuit. The radiation detection sensitivity of this PED after several test-irradiations to $^{137}Cs$ gamma radiation source appeared to be 1.85 cps/$Gy{\cdot}h^{-1}$ with 19.3% of the coefficient of variation, which satisfied the performance criteria for the active personnel radiation monitor. Further improvement of the electronic circuit and operating program will enable the PED to be used in personal monitoring purpose.

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Implementation of Digital Portable Radiation Detector with the Algorithm of Temperature Compensation (온도 보정 Algorithm을 적용한 Digital 휴대용 방사선 검출기의 구현)

  • Park, Ge-O;Lee, Jung-Hyun;Kim, Young-kil
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2016.10a
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    • pp.202-205
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    • 2016
  • Shipping and logistics safety, security system is strengthening worldwide, the development of shipping and logistics safety security core technology for national security logistics system construction has been carried out. Interest in portable radiation detection device capable detecting gamma rays nuclides is increasing. In this paper, I would like to propose the study of implementation of digital portable radiation detector with the algorithm of temperature compensation.

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Determination of Spectrum-Exposure Rate Conversion Factor for a Portable High Purity Germanium Detector (휴대형 고순도 게르마늄검출기에 대한 스펙트럼-조사선량율 변환연산자의 결정)

  • Kwak, Sang-Soo;Park, Chong-Mook;Ro, Seung-Gy
    • Journal of Radiation Protection and Research
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    • v.13 no.2
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    • pp.29-40
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    • 1988
  • A spectrum-exposure rate conversion operator G(E) for a portable HPGe detector used for field environmental radiation survey was theoretically developed on the basis of a space distribution function of gamma flux emitted from a disk source and an areal efficiency of the detector. The radiation exposure rates measured using this G(E) and the portable HPGe. detector connected to a portable multichannel analyzer were compared with those measured by a 3' ${\phi}\;{\times}$3' NaI(Tl) scintillation detector with the reported G(E) and a pressurized ionization chamber. A comparison of the three results showed that the result obtained using the HPGe detector was lower than those determined using the NaI(Tl) detector and ionization chamber by 17% to 29%, The difference obtained is close to that reported in literature. The method developed here can be easily applicable to obtain a G(E) factor suitable to any detector for detecting the exposure rate of environmental gamma radiation, since the spectrum-exposure rate conversion operator can be calculated by a hand calculator.

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The Study on Design of Semiconductor Detector for Checking the Position of a Radioactive Source in an NDT (비파괴검사 분야에서 방사선원의 위치 확인을 위한 반도체 검출기 설계에 관한 연구)

  • Kim, Kyo-Tae;Kim, Joo-Hee;Han, Moo-Jae;Heo, Ye-Ji;Ahn, Ki-Jung;Park, Sung-Kwang
    • Journal of the Korean Society of Radiology
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    • v.11 no.3
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    • pp.171-175
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    • 2017
  • In the non-destructive inspection field, we invest a lot of time and resources in developing the radiation source system to ensure the safety of the workers. However, the probability of accidents is still high. In order to prevent potential radiation accidents in advance, it is necessary to directly verify the position of the radiation source, but the research is still insufficient. In this study, we developed a monitoring system that can detect the position of the radiation source in the source guide tube in the gamma-ray irradiator. The characteristics of the radiation detector are estimated by monte carlo simulation. As a result, the radiation detector for Ir-192 gamma-ray energy was analyzed to have secondary electron equilibrium at $150{\mu}m$ regardless of the semiconductor material. Also, it is expected that the gamma ray response characteristic is the best in $HgI_2$. These results are expected to be used as a basis for determining the optimal thickness of the radiation detector located in the detection part of the future monitoring system. In addition, when developing a monitoring system based on this, radiation workers can easily recognize the danger and secure safety, as well as prevent and preemptively respond to potential radiation accidents.

A Study for Analysis of Image Quality Based on the CZT and NaI Detector according to Physical Change in Monte Carlo Simulation (CZT와 NaI 검출기 물질 기반 물리적 변화에 따른 영상의 질 분석에 관한 연구: 몬테카를로 시뮬레이션)

  • Ko, Hye-Rim;Yoo, Yu-Ri;Park, Chan-Rok
    • Journal of the Korean Society of Radiology
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    • v.15 no.5
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    • pp.741-748
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    • 2021
  • In this study, we evaluated image quality by changing collimator length and detector thickness using the Geant4 Application for Tomographic Emission (GATE) simulation tool. The gamma camera based on the Cadimium Zinc Telluride (CZT) and NaI detectors is modeled. In addition the images were acquired by setting 1, 2, 3, 4, 5, and 6 cm collimator length and 1, 3, 5, and 7 mm detector thickness using point source and phantom, which is designed by each diameter (4.45, 3.80, 3.15, 2.55 mm) with 447, 382, 317, and 256 Bq. The sensitivity (cps/MBq) for point source, and signal to noise ratio (SNR) and profile for phantom at the 4.45 mm by drwan the region of interests were used for quantitative analysis. Based on the results, the sensitivity according to collimator length is 2.3 ~ 48.6 cps/MBq for CZT detector, and 1.8 ~ 43.9 cps/MBq for NaI detector. The SNR using phantom is 3.6~9.8 for CZT detector, and 2.9~9.5 for NaI detector. As the collimator length is increased, the image resolution is also improved according to profile results based on the CZT and NaI detector. In addition, the senistivity for detector thickness is 0.04 ~ 0.12 cps/MBq for CZT detector, and 0.03 ~ 0.11 cps/MBq. The SNR using phnatom is 7.3~9.8 count for CZT detector, and 5.9~9.5 for NaI detector. As the detector thickness is increased, the image resolution is decreased according to profile results based on the CZT and NaI detector due to scatter ray. In conclusion, we need to set the geometric material such as detector and collimator to acuquire suitable image quality in nuclear medicine.

A readout method using pulse peak-time capture for radiation detectors (펄스의 피크시각 포착을 이용한 방사선 검출기의 신호처리 방법)

  • Kim, Jong-ho;Kwon, Young-mok;Hong, Hyoung-pyo;Che, Gyu-shik
    • Journal of Advanced Navigation Technology
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    • v.21 no.6
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    • pp.651-658
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    • 2017
  • There were many studies on the development of radiation measuring instruments to detect the presence of radiation. In particular, the signal processing method and treatment without loss of the detection signal are very important. The common feature for these studies is the peak-hold method that keeps the peak value of input signal uniform for a short time, readouts its value, discharges electrical value, and then waits for next signal. We propose the new methodology to capture the pulse peak value from the radiation detector and read the value directly other than peak-hold method. This method has merit of accurate reading the input signal pulse peak value without complicate process of holding for a period or initializing of input signal, and then be verified to be adequate through simulation of actual example.

Monte-carlo Simulation for X-ray Photon Counting using MPPC Arrays (배열형 실리콘광증배소자를 이용한 포톤 카운팅 검출기 설계를 위한 몬테칼로 시뮬레이션 연구)

  • Lee, Seung-Jae;Baek, Cheol-Ha
    • Journal of the Korean Society of Radiology
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    • v.12 no.7
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    • pp.929-934
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    • 2018
  • Studies for counting and detecting X-rays for the improvement of image quality and material analysis are active. In this work, the detector for X-ray photon counting was designed using Multi-pixel photon counter (MPPC) array and the detector characteristics were evaluated through simulation. Geant4 Application for Tomographic Emission (GATE) was used to obtain the position where the X-ray and the scintillation interacted, and this position was used as the light generation position of DETECT2000. 0.5 mm and 1 mm thick Gadolinium Aluminium Gallium Garnet (GAGG) scintillators were used and the light generated through a $4{\times}4$ array of MPPCs was acquired. The spatial resolution of the designed detector was evaluated by reconstructed image using the light signal acquired for each channel. We obtained images of more than 2 lp/mm in both 0.5 mm and 1 mm thick GAGG scintillation. When this detector is used in a X-ray system, a low-cost system capable of photon counting can be made.