• Title/Summary/Keyword: 무기섬광체

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Fabrication of Miniature Radiation Sensor Using Plastic Optical Fiber for Medical Usage (플라스틱 광섬유를 이용한 초소형 의료용 방사선 센서 제작)

  • Hwang, Young-Muk;Cho, Dong-Hyun;Cho, Hyo-Sung;Kim, Sin;Lee, Bong-Soo
    • Journal of radiological science and technology
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    • v.28 no.1
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    • pp.9-12
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    • 2005
  • In this study, film type radiation sensor tips are fabricated for remote sensing of X or g-ray with inorganic scintillators and plastic optical fiber. The visible range of light from the inorganic scintillator that is generated by X and g-ray is guided by the plastic optical fiber and is measured by optical detector and power-meter. It is expected that the fiber-optic radiation sensor which is possible to be developed based on this study is used for remote, fast and exact sensing of X or g-ray because of its characteristics such as very small size, light weight and no interference to electromagnetic fields.

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Preparation of polymeric composites for surface contamination measurement in order to characterize nuclear facilities decommissioning (원자력시설 해체 시 특성평가를 위한 표면오염 탐지 이중구조 고분자 복합체의 제조)

  • 한명진;서범경;우주희;이근우
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.97-104
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    • 2004
  • Double-layered polysulfone composite films, containing cerium activated yttrium silicate (CAYS) as a flour, were prepared from double casting of two polymeric solutions, and their morphology and physical strength were superior to those of single-layered composites. The prepared polymeric films consist of a dense bottom layer and a CAYS-holding top layer. The former is made of coagulating the polysulfone and methylene chloride binary solution and works as a supporter to improve the composite's physical strength, while the latter holding the inorganic fluor plays a role as an active site to detect the radioactive contamination. The prepared films revealed two distinguished, but tightly attached, double layers, their attachment being identified by morphology of the interface between two layers. As prepared by water immersion coagulation, the films have highly developed macropores, compared with a dense structure in the film prepared by evaporation. In the radionuclide detection test of the CAYS-impregnated composites, the films have reliable detection capacity at a radionuclide spotting test. The double-layered composites with the dense support layer show a better stability in holding the radionuclides spotted on the surface as well as an improvement in physical strength, compared with the single-layer composites having shortcomings such as being too porous or being brittle.

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Preparation and Radionuclide Detection Analysis of Inorganic Fluor Impregnated Double-layered Membranes (이중구조 무기형광 함침막 제조 및 방사성핵종 탐지능력의 분석)

  • 이근우;서범경;박진호;남석태;한명진
    • Membrane Journal
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    • v.12 no.4
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    • pp.240-246
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    • 2002
  • New polysulfone scintillation proximity membranes were prepared by impregnating Cerium Activated Yttrium Silicate (CAYS), an inorganic fluor, in a membrane structure. The membranes were applied to detect the radionuclide contamination directly without the aid of a scintillation cocktail. The preparation of membranes was divided into two processes. A supporting polymer film was made of casting solutions consisting of polysulfone and solvent, their cast film being solidified by vacuum evaporation. CAYS-dispersed polymer solutions were cast over the first, solidified polymer films and coagulated either by evaporating solvent or by exchanging solvent in the solution with nonsolvent in a coagulation bath. The prepared membranes had two distinguished, but tight1y attached, double layers: one is the supporting layer of dense polymer film and the other the detecting layer consisting of CAYS and polymer. The radionuclide counting results revealed that the prepared membranes were efficient to monitor radioactivity contamination with reliable counting ability.

Fabrication and characterization of plastic fiber-optic radiation sensor tips using inorganic scintillator material (무기 섬광체를 이용한 플라스틱 광섬유 방사선 센서부 제작 및 특성평가)

  • Hwang, Young-Muk;Cho, Dong-Hyun;Lee, Bong-Soo;Cho, Hyo-Sung;Kim, Sin
    • Journal of Sensor Science and Technology
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    • v.14 no.4
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    • pp.244-249
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    • 2005
  • In this study, radiation sensor tips are fabricated for remote sensing of X or gamma ray with inorganic scintillators and plastic optical fiber. The visible range of light from the inorganic scintillator that is generated by radiation source is guided by the plastic optical fiber and is measured by optical detector and power-meter. Two kinds of sensor tips are designed and fabricated such as film type and powder type. Many kinds of inorganic scintillators are used to fabricate both sensor tips, and the different wavelength of emitting lights from them are measured to determine the optimal inorganic scintillator which has maximum light output. As a radiation source X-ray generator and Ir-192 are selected to test a performance of sensor tip. It is expected that the fiber-optic radiation sensor is widely used in nuclear industry and medical applications due to its special characteristics such as good flexibility, easy in processing, long lengths and no interference to electro magnetic field.

Determination of carbon-14 and tritium in a PWR spent nuclear fuel (PWR 사용후핵연료 중 탄소-14 및 트리튬 정량)

  • Kim, Jung Suk;Park, Soon Dal;Lee, Chang Hun;Song, Byong Chul;Jee, Kwang Yong
    • Analytical Science and Technology
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    • v.18 no.4
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    • pp.298-308
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    • 2005
  • The methods for determining C-14 and tritium contents in the spent nuclear fuel sample were developed. The carbon-14($^{14}CO_2$) released during the dissolution of the spent fuel sample and $CaCO_3$ ($CO_2$ carrier) with 8 M $HNO_3$ at $90^{\circ}C$ was collected in trap containing 1.5 M NaOH. The volatile radioactive iodine evolved when the spent fuel was dissolved, was trapped on to Ag-silicagel (Ag-impregnated silicagel) adsorbent in column which is connected to two NaOH traps. The solutions which contain tritium as HTO after fuel dissolution were decontaminated by deionization with a mixture of cation and anion exchange resins and inorganic ionexchangers. The amount of C-14 in the trap solutions and the HTO concentration in the resulting deionization water were then determined by liquid scintillation counting.