• Title/Summary/Keyword: Detector materials

Search Result 503, Processing Time 0.029 seconds

Characteristics of a new cone beam computed tomography

  • Park, Chang-Seo;Kim, Kee-Deog;Park, Hyok;Jeong, Ho-Gul;Lee, Sang-Chul
    • Imaging Science in Dentistry
    • /
    • v.37 no.4
    • /
    • pp.205-209
    • /
    • 2007
  • Purpose: To determine the physical properties of a newly developed cone beam computed tomography (CBCT). Materials and Methods: We measured and compared the imaging properties for the indirect-type flat panel detector (FPD) of a new CBCT and the single detector array (SDA) of conventional helical CT (CHCT). Results: First, the modulation transfer function (MTF) of the CBCT were superior to those of the CHCT. Second, the noise power spectrum (NPS) of the CBCT were worse than those of the CHCT. Third, detective quantum efficiency (DQE) of the indirect-type CBCT were worse than those of the CHCT at lower spatial frequencies, but were better at higher spatial frequencies. Although the comparison of contrast-to-noise ratio (CNR) was estimated in the limited range of tube current, CNR of CBCT were worse than those of CHCT. Conclusion: This study shows that the indirect-type FPD system may be useful as a CBCT detector because of high resolution.

  • PDF

Scanning confocal microscope using a quad-detector (4분할 photodiode를 이용한 scanning confocal microscope)

  • 유석진;김수철;이진서;권남익
    • Korean Journal of Optics and Photonics
    • /
    • v.8 no.2
    • /
    • pp.165-168
    • /
    • 1997
  • We have constructed a scanning confocal microscope using a 780 nm semiconductor laser, an actuator of a compact disk player and a quad-detector. This device detects heights and characteristics of a surface. The laser focus was located at the surface of a sample by using the error signal obtained by a quad-dector, and the current supplied to the actuator for lens was displayed as a height. The materials of a surface were classified according to reflected total intensities and was displayed by different color in a monitor. The device has very samll dimensions of 30 mm$\times$20 mm$\times$20 mm and scan field is 1.6 mm$\times$1.6mm. We obtained two images, one using only reflected light and the other using an error signal from a quad-detector and compared these two images.

  • PDF

An Experimental Study for the Minimization of Soot Adsorption on the Optical Surface of an Engine Soot Detector (I) (엔진 수트 측정 센서 표면에서의 흡착 오염 저감을 위한 실험적 연구 (I))

  • Yoon Eui-Sung;Kim Hak-Yal;Kong Hosung;Han Hung-Gu
    • Tribology and Lubricants
    • /
    • v.20 no.6
    • /
    • pp.343-349
    • /
    • 2004
  • The adsorption of soot particles onto a sensor surface of the engine soot detector posses a critical problem in the measurement. In order to prevent the optical rod surface from soot contamination, various functional coatings and flow-induced cleaning were applied to the surface in this work. For surface coatings, various materials of self-assembled monolayers (SAM) such as OTS (octadecyltrichlorosilane), PFDTES (perfluorodecyl-triethoxysilane) and PFDTMS (perfluorodecyltrimethoxysilane) were coated on the optical rod surface ,which have different characteristics in both hydrophobicity and oleophobicity. These coatings were tested with soot content varying from $0\%\;to\;3wt\%$ and oil temperature from 20 to $70^{\circ}C$. Test results showed that surface coatings were not effective for preventing the adsorption of soot panicles on the surface of optical rod. It was thought that these coatings provided the surface with additional attractive surface forces. However, it was found that adsorption of soot particles onto a sensor surface was minimized by flow-induced cleaning. This effect was tested with varying the flow velocity.

ACSR Inner Corrosion Detection by Eddy Current Sensor (와전류센서를 이용한 ACSR 전선의 내부부식 검출)

  • 강연욱;강지원;양병모;정재기
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
    • /
    • v.12 no.1
    • /
    • pp.12-19
    • /
    • 1998
  • This paper deals with ACSR(Aluminum Conductor Steel Reinforced) inner corrosion detection using a detector which automatically runs on an ACSR distribution line and inspects the inner corrosion of the conductor by utilization of the nondestructive eddy current test. According to corrosion appearance and development of ACSR, the impedance change of the eddy current coils is theoretically verified. And then specifications and performances of the detector are described. Experimental procedures and desirable test results are reported. In conclusion, this detector can realize the nondestructive detecting of an ACSR inner corrosion. Upgrading the maintenance efficiency and improving the reliability of distribution line, whether is covered with insulating materials or not, would be expected by this nondestructive test method.method.

  • PDF

The Electrical and Radiation Detection Properties of $Au/Cd_{1-x}Zn_x/Te(x=20%)/Au$ Structure ($Au/Cd_{1-x}Zn_x/Te(x=20%)/Au$ 구조의 전기적 특성 및 방사선 탐지 특성)

  • 최명진;왕진석
    • Electrical & Electronic Materials
    • /
    • v.10 no.1
    • /
    • pp.39-44
    • /
    • 1997
  • Bulk type radiation detector of Au/Cd$_{1-x}$ Zn$_{x}$Te(x=20%)/Au structure using Cd$_{1-x}$ Zn$_{x}$Te(x=20%) wafer(3x4xl mm$^{3}$) grown by high pressure Bridgman method has been developed. We etched wafer surfaces with 2% Br-methanol solution and coated gold thin film on the surfaces by electroless deposition method for 5 min. in 49/o HAuCI$_{3}$ 4H20 solution. Initial etch rates of Cd, Zn and Te were 46%, 12% and 42% respectively. After etched, the surface of wafer was slightly revealed to Te rich condition. The leakage current was increased with etch time, but it didn't exceed 3nA at 50volt. The thickness of Au film was about 100nm by Rutherford Backscattering Spectroscopy(RBS). The resolution were 6.7% for 22.1 keV photon from 109 $^{109}$ Cd and 8.2% for 59.5 keV photon from $^{241}$ Am. The radiation detector such as Au/Cd$_{1-x}$ Zn$_{x}$Te(x=20%)/Au structure was more effective to monitor the low energy gamma radiation.iation.

  • PDF

Determination of Si (Li) Detector Efficiency Using Electro-Deposition Sources in 5-15 keV Photon Energy Range (5-15 keV 에너지 범위에서 전기증착 선원을 사용한 Si (Li) 검출기 효율결정)

  • Jeon, Woo-Ju;Park, Tae-Soon;Hwang, Sun-Tae;Joo, Koan-Sik
    • Nuclear Engineering and Technology
    • /
    • v.26 no.4
    • /
    • pp.548-554
    • /
    • 1994
  • The full-energy peak efficiency for a collimated geometry of a Si (Li) detector has been experimentally determined using the electro-deposition sources. The radioactive sources of $^{51}$ Cr, $^{54}$ Mn, $^{57}$ Co and $^{65}$ Zn nuclides are prepared by the electro-deposition method. The measured efficiency values are corrected for the escape losses due to the K X-rays of silicon and the absorptions in materials related to source-to-detector geometry. The corrected efficiency values have turned out to be nearly constant regardless of photon energy.

  • PDF

Conceptual design of neutron measurement system for input accountancy in pyroprocessing

  • Lee, Chaehun;Seo, Hee;Menlove, Spencer H.;Menlove, Howard O.
    • Nuclear Engineering and Technology
    • /
    • v.52 no.5
    • /
    • pp.1022-1028
    • /
    • 2020
  • One of the possible options for spent-fuel management in Korea is pyroprocessing, which is a process for electrochemical recycling of spent nuclear fuel. Nuclear material accountancy is considered to be a safeguards measure of fundamental importance, for the purposes of which, the amount of nuclear material in the input and output materials should be measured as accurately as possible by means of chemical analysis and/or non-destructive assay. In the present study, a neutron measurement system based on the fast-neutron energy multiplication (FNEM) and passive neutron albedo reactivity (PNAR) techniques was designed for nuclear material accountancy of a spent-fuel assembly (i.e., the input accountancy of a pyroprocessing facility). Various parameters including inter-detector distance, source-to-detector distance, neutron-reflector material, the structure of a cadmium sleeve around the close detectors, and an air cavity in the moderator were investigated by MCNP6 Monte Carlo simulations in order to maximize its performance. Then, the detector responses with the optimized geometry were estimated for the fresh-fuel assemblies with different 235U enrichments and a spent-fuel assembly. It was found that the measurement technique investigated here has the potential to measure changes in neutron multiplication and, in turn, amount of fissile material.

Influence of the Thin-Film Ag Electrode Deposition Thickness on the Current Characteristics of a CVD Diamond Radiation Detector

  • Ban, Chae-Min;Lee, Chul-Yong;Jun, Byung-Hyuk
    • Journal of Radiation Protection and Research
    • /
    • v.43 no.4
    • /
    • pp.131-136
    • /
    • 2018
  • Background: We investigated the current characteristics of a thin-film Ag electrode on a chemical vapor deposition (CVD) diamond. The CVD diamond is widely recognized as a radiation detection material because of its high tolerance against high radiation, stable response to various dose rates, and good sensitivity. Additionally, thin-film Ag has been widely used as an electrode with high electrical conductivity. Materials and Methods: Considering these properties, the thin-film Ag electrode was deposited onto CVD diamonds with varied deposition thicknesses (${\fallingdotseq}50/98/152/257nm$); subsequently, the surface thickness, surface roughness, leakage current, and photo-current were characterized. Results and Discussion: The leakage current was found to be very low, and the photo-current output signal was observed as stable for a deposited film thickness of 98 nm; at this thickness, a uniform and constant surface roughness of the deposited thin-film Ag electrode were obtained. Conclusion: We found that a CVD diamond radiation detector with a thin-film Ag electrode deposition thickness close to 100 nm exhibited minimal leakage current and yielded a highly stable output signal.

Design and characterization of a Muon tomography system for spent nuclear fuel monitoring

  • Park, Chanwoo;Baek, Min Kyu;Kang, In-soo;Lee, Seongyeon;Chung, Heejun;Chung, Yong Hyun
    • Nuclear Engineering and Technology
    • /
    • v.54 no.2
    • /
    • pp.601-607
    • /
    • 2022
  • In recent years, monitoring of spent nuclear fuel inside dry cask storage has become an important area of national security. Muon tomography is a useful method for monitoring spent nuclear fuel because it uses high energy muons that penetrate deep into the target material and provides a 3-D structure of the inner materials. We designed a muon tomography system consisting of four 2-D position sensitive detector and characterized and optimized the system parameters. Each detector, measuring 200 × 200 cm2, consists of a plastic scintillator, wavelength shifting (WLS) fibers and, SiPMs. The reconstructed image is obtained by extracting the intersection of the incoming and outgoing muon tracks using a Point-of-Closest-Approach (PoCA) algorithm. The Geant4 simulation was used to evaluate the performance of the muon tomography system and to optimize the design parameters including the pixel size of the muon detector, the field of view (FOV), and the distance between detectors. Based on the optimized design parameters, the spent fuel assemblies were modeled and the line profile was analyzed to conduct a feasibility study. Line profile analysis confirmed that muon tomography system can monitor nuclear spent fuel in dry storage container.

The effect of front edge on efficiency for point and volume source geometries in p-type HPGe detectors

  • Esra Uyar ;Mustafa Hicabi Bolukdemir
    • Nuclear Engineering and Technology
    • /
    • v.54 no.11
    • /
    • pp.4220-4225
    • /
    • 2022
  • Monte Carlo (MC) simulations are increasingly being used as an alternative or supplement to the gamma spectrometric method in determining the full energy peak efficiency (FEPE) necessary for radionuclide identification and quantification. The MC method is more advantageous than the experimental method in terms of both cost and time. Experimental calibration with standard sources is difficult, especially for specimens with unusually shaped geometries. However, with MC, efficiency values can be obtained by modeling the geometry as desired without using any calibration source. Modeling the detector with the correct parameters is critical in the MC method. These parameters given to the user by the manufacturer are especially the dimensions of the crystal and its front edge, the thickness of the dead layer, dimensions, and materials of the detector components. This study aimed to investigate the effect of the front edge geometry of the detector crystal on efficiency, so the effect of rounded and sharp modeled front edges on the FEPE was investigated for <300 keV with three different HPGe detectors in point and volume source geometries using PHITS MC code. All results showed that the crystal should be modeled as a rounded edge, especially for gamma-ray energies below 100 keV.