• Title/Summary/Keyword: 방사선 검출기

Search Result 569, Processing Time 0.026 seconds

A Study on Efficiency Error in Distance Inverse Square Law using Cylinder NaI(Tl) Scintillation Detector (원통형 NaI(Tl) 신틸레이션 검출기를 이용한 거리의 역자승 법칙에서 효율 오류에 대한 연구)

  • Lee, Samyol;Yoon, Jungran;Ro, TaeIk
    • Journal of the Korean Society of Radiology
    • /
    • v.7 no.5
    • /
    • pp.333-338
    • /
    • 2013
  • Generally, it's known fact that intensity of radioactivity satisfies inverse-square law. However, the law was dissatisfied with practical experiment because of limited shape of scintillation detector. Especially, in the case of near distance between the surface of detector and the radioactive source, the difference grows larger. In the present study, reason of this difference was confirmed by experiment with $2^{{\prime}{\prime}}{\times}2^{{\prime}{\prime}}{\phi}$ NaI(Tl) scintillation detector and $^{60}Co$(1.174 MeV, 1.333 MeV)and $^{137}Cs$(0.662 MeV) gamma ray sources. From the experiment, the correction coefficient was obtained with gamma ray detection efficiency and geometrical volume. In the result of the present study, the efficiency difference of the detector was corrected with the coefficient. In the present result, we obtained that the inverse-square law experiment have to consider the efficiency and geometrical value of the detector.

Design of Wide-Range radiation measurement system using GM Tube and NaI(TI) Detector (GM Tube 및 NaI(TI) 검출기를 사용한 Wide-Range 방사선 측정 시스템의 설계)

  • Ra, Seung-Tak;Lee, Joo-Hyun;Lee, Seung-Ho
    • Journal of IKEEE
    • /
    • v.21 no.2
    • /
    • pp.146-149
    • /
    • 2017
  • In this paper, we propose a wide-range radiation measurement system using GM Tube and NaI(TI) detector. The proposed system is designed as a small module optimized to control and count the detector signal of NaI(Tl) Detector and GM Tube. The radiation dose is measured in a wide-range 0.1uSv/h to 10mSv/h in conjunction with two detectors, and two detectors operate simultaneously at 10uSv/h to 100uSv/h, where the measurement interval overlaps. The radiation dose was selected using a wide-range radiation measurement algorithm that controls the on/off function of the detector in the appropriate interval for the overlapped radiation measurable interval. In order to evaluate the performance of the proposed system, it has been confirmed that the measurement uncertainty of each section is measured as ${\pm}7.5%$ and it operates normally under ${\pm}15%$ of the international standard.

Design of a Radiation Spectroscopy Detector using a Spherical Scintillator and Development of a Radiation Source Position Tracking System (구형의 섬광체를 이용한 방사선 스펙트로스코피 검출기 설계 및 방사선원 위치 추적 시스템 개발)

  • Lee, Seung-Jae
    • Journal of the Korean Society of Radiology
    • /
    • v.14 no.6
    • /
    • pp.725-731
    • /
    • 2020
  • A radiation spectroscopy detector using a spherical scintillator was designed, and a system was developed to track the position of a radiation source using several detectors. The position tracking algorithm was designed based on the theory that the number of radiations decreases according to the inverse square law of distance, and the position of the radiation source was calculated by measuring the number of radiations generated from the radiation sources at various positions. The radiation generated from the radiation source is detected by different coefficients in each detector, and the difference between these detected coefficients varies in proportion to the inverse square of the distance. Geant4 Application for Tomographic Emission (GATE) simulation was performed to verify and evaluate the performance of the designed radiation source position tracking system, and radiation generated from radiation sources placed at different positions was counted with each detector. The number of measured radiations was tracked through the radiation source position tracking algorithm, and the error between the actual radiation source position and the position calculated by the algorithm was evaluated. The error between the position of the actual radiation source and the calculated position was measured as an average of 0.11% on the X-axis and 0.37% on the Y-axis, and it was verified that the position can be measured very accurately.

Implementation of A9-Based Digital Portable Radiation Detector with the Algorithm of Temperature Compensation in Scintillator (Scintillator에 온도 보정 알고리즘을 적용한 A9기반의 디지털 휴대용 방사선 검출기 구현)

  • Lim, Ik-Chan;Park, Geo;Kim, Young-kil
    • Journal of the Korea Institute of Information and Communication Engineering
    • /
    • v.21 no.10
    • /
    • pp.1981-1989
    • /
    • 2017
  • In accordance with the global strengthening of security systems for the safety of the shipping and logistics industry, the development of core technologies within the field has become a key in the establishment of Korea's own national logistics security system. Further in line with these global developments, there is growing attention within Korea to the development of portable radiation detectors capable of detecting gamma ray nuclides. In addition, many parts are becoming localized. In this research, instead of Pulse Shaping Board, which is used in existing portable radiation detectors, we have implemented an Algorithm to discriminate nuclides and correct the temperature conversion efficiency of the scintillator. This paper aims to improve the performance of these devices through the implementation of a temperature conversional algorithm within the scintillator of the A9-based digital portable radiation detector.

Assessment of Dosimetric Leaf Gap According to Measuring Active Volume of Detector (검출기 측정 용적에 따른 Dosimetric Leaf Gap 변화와 정확성 검증에 대한 연구)

  • Dae-Hyun, Kim
    • Journal of the Korean Society of Radiology
    • /
    • v.16 no.7
    • /
    • pp.863-870
    • /
    • 2022
  • DLG (Dosimetric Leaf Gap) and transmission factor are important parameters of MLC modeling in treatment planning system. In this study, DLG and transmission factor of HD-MLC were measured using detector with different measuring volumes, and the accuracy of the treatment plans was evaluated according to the DLG values. DLG was measured using the dynamic sweeping gap method with Semiflux3D and MicroDiamond detectors. Then, 10 radiation treatment plans were generated to optimize the DLG value and compared with the measurement results. Photon energies 6, 8, 10 MV, the DLG measured by Semiflux3D were 0.76, 0.83, and 0.85 mm, and DLG measured by MicroDiamond were 0.78, 0.86, and 0.9 mm. All plans were measured by portal dosimetry and analyzed using Gamma Evaluation. In the 6 MV photon beams, the average gamma passing rate were 94.3% and 98.4% for DLG 0.78 mm and 1.15 mm. In the 10 MV photon beam, the average gamma passing rate were 91.2% and 97.6% for DLG 0.9 mm and 1.25 mm. HD-MLC needs accurate modeling in the treatment planning system. DLG could be used measured data using small volume detector. However, for better radiation therapy, DLG should be optimized at the commissioning stage of LINAC.

Au 전극을 적용한 방사선 영상 검출기의 전기적 특성 평가

  • Song, Yong-Geun;O, Gyeong-Min;Kim, Seong-Heon;Kim, Ji-Na;No, Seong-Jin;Heo, Seung-Uk;Nam, Sang-Hui
    • Proceedings of the Korean Vacuum Society Conference
    • /
    • 2012.02a
    • /
    • pp.365-365
    • /
    • 2012
  • 본 연구에서는 X-ray 영상을 얻기 위한 검출기 중 직접 검출방식에 쓰이고 있는 광도전체(Photoconductor)의 전극으로 Au를 사용하여 전기적인 특성을 파악하였다. Au는 유기물에 대한 반응이 적고 전기 전도도가 좋은 물질로서 투명전극으로 많이 쓰이고 있는 인듐 주석 산화물(ITO)을 대체할 수 있는 물질로 각광받고 있다. 우선 시편 제작을 위해 투명한 기판(Corning Glass, 0.7t)위에 하부전극으로 Au를 $3cm{\times}3cm$의 크기로 Physical Vapor Deposition(PVD) 방식을 이용하여 증착하였다. 이 때 챔버 내 저진공은 Rotary Pump를 이용하여 $3.9{\times}10-2Torr$ 이하를 유지하고 고진공은 Diffusion Pump를 이용하여 $5.3{\times}10-5Torr$ 이하를 유지하였다. 완성된 하부전극 위에 광도전체인 $HgI_2$를 폴리머 물질에 교반하여 메탈 폴리머 결합을 가진 Paste를 제조하고 이 Paste를 Screen Printing Method를 이용하여 증착 후 건조하였다. 마지막으로 시편위에 상부전극을 하부전극과 같은 조건으로 증착함으로서 시편을 완성한다. 상하부 전극으로 쓰이는 Au의 증착 조건을 변화시키면서 그에 따른 시편의 전기적인 특성 변화를 관찰하였다. 그 결과, Au의 증착온도와 질량에 따라 특성이 변화함을 알 수 있었다. 본 연구의 결과를 통해 디지털 방사선 검출기에서 Au 전극의 적용 가능성을 확인하였으며, 추후 Au 증착 조건의 최적화를 통해 방사선 검출기의 효율 향상을 위한 연구를 하고자 한다.

  • PDF

The Study for the analysis of the detection efficiency and the design of the radiation detector's collimator using MCNP (MCNP 기반 스테레오 방사선 검출기 콜리메이터 설계 및 선량검출효율 분석연구)

  • Hwang, Young-Gwan;Lee, Nam-Ho;Kang, Gi-Byong;Park, Jong-Won
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
    • /
    • 2013.05a
    • /
    • pp.1017-1019
    • /
    • 2013
  • The radiation sources leaked from large-scale radiation leak accident like the Hukushima nuclear power plant accident or nuclear explosions can cause to the very large damage for us. So that the damage can be minimized, we have being developed a detector that can providing information about the location of the source to remove dangerous substances quickly than the conventional single detector. In this paper, we designed the shielding and collimator for the development of the Stereo Radiation detector in order to detect contaminants using MCNP Code. And we analyzed the results that is detected from the discretionary position of the radiation source. The results of this paper will be used as the basis for designing efficient structure for the radiation detectors.

  • PDF