• 제목/요약/키워드: Gamma-ray spectroscopy

검색결과 125건 처리시간 0.024초

New mathematical approach to calculate the geometrical efficiency using different radioactive sources with gamma-ray cylindrical shape detectors

  • Thabet, Abouzeid A.;Hamzawy, A.;Badawi, Mohamed S.
    • Nuclear Engineering and Technology
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    • 제52권6호
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    • pp.1271-1276
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    • 2020
  • The geometrical efficiency of a source-to-detector configuration is considered to be necessary in the calculation of the full energy peak efficiency, especially for NaI(Tl) and HPGe gamma-ray spectroscopy detectors. The geometrical efficiency depends on the solid angle subtended by the radioactive sources and the detector surfaces. The present work is basically concerned to establish a new mathematical approach for calculating the solid angle and geometrical efficiency, based on conversion of the geometrical solid angle of a non-axial radioactive point source with respect to a circular surface of the detector to a new equivalent geometry. The equivalent geometry consists of an axial radioactive point source with respect to an arbitrary elliptical surface that lies between the radioactive point source and the circular surface of the detector. This expression was extended to include coaxial radioactive circular disk source. The results were compared with a number of published data to explain how significant this work is in the efficiency calibration procedure for the γ-ray detection systems, especially in case of using isotropic radiating γ-ray sources in the form of point and disk shapes.

γ-ray Radiation Induced Synthesis and Characterization of α-Cobalt Hydroxide Nanoparticles

  • Kim, Sang-Wook;Kwon, Bob-Jin;Park, Jeong-Hoon;Hur, Min-Goo;Yang, Seung-Dae;Jung, Hyun
    • Bulletin of the Korean Chemical Society
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    • 제31권4호
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    • pp.910-914
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    • 2010
  • A novel synthetic route has been developed to prepare $\alpha$-cobalt hydroxide with intercalated nitrate anions. It was successfully synthesized by $\gamma$-ray irradiation under simple conditions, i.e., air atmosphere, without base. Under $\gamma$-ray irradiation, it leads to the formation of layered cobalt hydroxynitrate compounds which have small crystalline size and have the role of a generator of hydroxyl anion. Structural and morphological characterizations were performed by using power X-ray diffraction (XRD), field emission scanning electron microscopy (FE-SEM), and high resolution transmission electron microscopy (HR-TEM). The component and thermal stability of the sample were respectively measured by Fourier transform infrared (FT-IR) spectroscopy, elemental analysis, and thermal analyses, including thermogravimetry (TG) and differential thermal analysis (DTA).

An investigation of the nuclear shielding effectiveness of some transparent glasses manufactured from natural quartz doped lead cations

  • Kassem, Said M.;Ahmed, G.S.M.;Rashad, A.M.;Salem, S.M.;Ebraheem, S.;Mostafa, A.G.
    • Nuclear Engineering and Technology
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    • 제53권6호
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    • pp.2025-2037
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    • 2021
  • The influence of lead cations on natural quartz (QZ) from Egypt as a glass shielding material for the composition with nominal formula (10Na2O - (90 - x) QZ - xPbO (where x = 30, 35, 40, 45 and 50 mol %)) was examined. The studied samples are synthesized via the melt quenching method at 1050 ℃. The X-ray diffraction XRD patterns were confirmed the glass nature for studied samples. Moreover, the optical properties, and the transparency for all compositions were examined by UV-Vis spectroscopy. Also, the major elemental composition of the natural quartz were estimated via the X-ray fluorescence (XRF) technique. Further, the density and molar volume were determined. Furthermore, the nuclear shielding parameters such as, mass attenuation coefficient, effective atomic number, electronic density, the total atomic, and electronic cross sections as well as the mean free path, and the half value layer with different gamma ray energies (81 keV-1407 keV) were calculated. Besides, the results showed that the shielding behavior towards the gamma ray radiation for all glass samples was increased as the increment in PbO concentration in the glass system.

FRAM을 이용한 우라늄 농축도 분석의 신뢰성 평가 연구 (Uranium Enrichment Analysis with Gamma-ray Spectroscopy)

  • 엄성호;정혜균;박준식;박세환;신희성
    • Journal of Radiation Protection and Research
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    • 제36권1호
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    • pp.16-23
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    • 2011
  • 보다 정확한 우라늄 농축도 분석은 핵물질 관리를 위하여 중요하다. 본 연구에서는 감마선을 이용한 우라늄 농축도 분석에서 시료와 검출기 사이에 차폐체가 있는 경우와 측정시간 변화에 따른 분석결과에 대한 정확성 평가 및 오차분석을 수행하였다. 우라늄 농축도를 분석하기 위하여 FRAM (Fixed energy Response function Analysis with Multiple efficiencies)을 이용하였다. FRAM에 의한 분석결과의 정확성은 화학 분석 결과와의 비교를 통해 평가되었다. 연구결과 선원과 검출기사이에 차폐체가 존재할 경우 차폐체의 두께변화에 따른 감마선의 세기는 지수함수 형태로 감소하며 감마선에너지 피이크의 반치폭 (FWHM : Full Width at Half Maximum)은 차폐체의 두께에 영향을 거의 받지 않는 것을 보였다. 따라서 시료와 검출기 사이에 차폐체가 있는 경우의 우라늄 농축도 분석에서 FRAM을 이용한 감마선분광 분석은 유용하게 활용될 수 있다. 본 연구 결과는 차폐체 안에 우라늄이 있는 경우 핵물질 분석에 기여할 수 있을 것이 기대된다.

감마선 분광분석을 위한 실리콘 광 증배소자 기반 Ce:GAGG 섬광검출기의 분광특성 연구 (Spectroscopic Properties of a Silicon Photomultiplier-based Ce:GAGG Scintillation Detector and Its Applicability for γ-ray Spectroscopy)

  • 박혜민;김정호;김동성;주관식
    • Journal of Radiation Protection and Research
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    • 제40권2호
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    • pp.73-78
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    • 2015
  • 본 연구에서는 실리콘 광 증배소자(Silicon photomultiplier)와 Ce:GAGG 섬광체 단결정을 이용한 섬광검출기를 제작하고, 감마선 분광특성 분석을 통해 기존에 상용화된 LYSO, CsI:Tl 섬광체와의 분광특성을 비교하였다. 섬광체 단결정의 크기는 $3{\times}3{\times}20mm^3$ 이며 $3{\times}3mm^2$ 실리콘 광 증배소자를 이용하여 섬광검출기를 제작한 후, 표준 감마선원인 $^{133}Ba$, $^{22}Na$, $^{137}Cs$, $^{60}Co$에 대한 에너지 분해능을 각각 측정하고 비교하였다. 그 결과 Ce:GAGG 섬광검출기의 감마선에 대한 에너지 분해능은 $^{133}Ba$ 0.356 MeV에서 13.5%, $^{22}Na$ 0.511 MeV에서 6.9%, $^{137}Cs$ 0.662 MeV에서 5.8% 그리고 $^{60}Co$ 1.33 MeV에서 2.3%의 분광 특성을 확인 할 수 있었다.

APPLICATION OF ALANINE/ESR SPECTRUM SHAPE CHANGE IN GAMMA DOSIMETRY

  • Choi, Hoon;Kim, Jeong-In;Lee, Byung-Ill;Lim, Young-Ki
    • Nuclear Engineering and Technology
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    • 제42권3호
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    • pp.313-318
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    • 2010
  • Alnine pellets were installed in a nuclear power plant for one or two operation cycles and measured by electron spin resonance (ESR) spectrometers for dosimetry. Dose and "x/y ratio", i.e., satellite peak over main center peak ratio, were measured for the returned alanine dosimeters from the nuclear power plant and compared to the values of reference alanine dosimeters exposed only to gamma rays. The variation of the x/y ratio change depended on the population of radicals from each radiation component with different LET. The gamma dose in a mixed radiation field was estimated by an additive gamma ray irradiation experiment and the measured dose rate at specified locations in the containment building.

베타/감마 동시 측정용 광섬유 이중 검출기의 개발을 위한 기초연구 (Feasibility Study on Development of a Fiber-Optic Dual Detector to Measure Beta- and Gamma-rays Simultaneously)

  • 홍승한;신상훈;심혁인;김선근;전혜수;장재석;김재석;권구원;장경원;유욱재;이봉수
    • 전기학회논문지
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    • 제63권2호
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    • pp.284-290
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    • 2014
  • A fiber-optic beta/gamma dual detector system with two types of sensing probes was fabricated to detect the beta- and gamma-rays simultaneously. As scintillators of the sensing probe type 1, two different inorganic scintillators, $CaF_2(Eu)$ and LYSO(Ce) crystals, were used to obtain the each scintillating efficiency with respect to beta-and gamma-rays and the inherent energy spectra of radioactive isotopes. In the case of the sensing probe type 2, which is composed of two identical inorganic scintillators and a beta shielding material based on the lead, it could discriminate beta- and gamma-rays using a subtraction method. In conclusion, we demonstrated that the proposed fiber-optic beta/gamma dual detector could measure and discriminate beta- and gamma-rays using both energy spectroscopy and subtraction method.

Ag-V/γ-Al2O3 촉매상에서 탄화수소-Selective Catalytic Reduction에 의한 질소산화물 저감 (DeNOx by Hydrocarbon-Selective Catalytic Reduction on Ag-V/γ-Al2O3 Catalyst)

  • 김문찬;이철규
    • 공업화학
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    • 제16권3호
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    • pp.328-336
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    • 2005
  • 본 연구에서는 배출가스 중에 포함된 NO를 비선택적 촉매환원법으로 환원시켜 제거하기 위하여 Ag와 V의 함량을 여러 가지로 달리하여 ${\gamma}-Al_2O_3$에 담지한 촉매를 제조하였고, 제조한 촉매에 대하여 온도, 산소농도, 아황산가스농도의 변화에 따른 $NO_x$의 전환율에 대하여 연구하였다. 또한 제조한 촉매의 물성분석을 통하여 촉매의 상태와 $NO_x$의 전환율과의 관계를 알아보았다. $AgV/{\gamma}-Al_2O_3$ 촉매의 경우에는 고온에서는 $Ag/{\gamma}-Al_2O_3$ 촉매보다 낮은 $NO_x$ 전환율을 나타내는 반면에 저온에서는$Ag/{\gamma}-Al_2O_3$ 촉매보다 높은 $NO_x$ 전환율을 나타내었고, 반응가스 중에 $SO_2$가 함유되어 있어도 $NO_x$의 전환율이 낮아지지 않았다. 반응실험 전 후의 촉매에 대하여 X-ray Diffraction, X-ray Photo electron Spectroscopy, Temperature Programmed Reduction, Ultraviolet-Visible Diffuse Reflectance Spectroscopy 등의 분석결과와 반응실험 결과를 비교하여 볼 때 V가 포함됨으로 인하여 Ag의 산화상태가 잘 유지되지 못하여 고온에서는 $NO_x$ 전환율이 낮아지며, $300^{\circ}C$ 이하의 저온에서는 V의 촉매작용으로 인하여 $NO_x$ 전환율이 높아진 것으로 나타났다.

MATERIAL INVESTIGATION AND ANALYSIS USING CHARACTERISTIC X-RAY

  • Oh, Gyu-Bum;Lee, Won-Ho
    • Nuclear Engineering and Technology
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    • 제42권4호
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    • pp.426-433
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    • 2010
  • The characteristic X-rays emitted from materials after gamma ray exposure was simulated and measured. A CdTe semiconductor detector and a $^{57}Co$ radiation source were used for energy spectroscopy. The types of materials could be identified by comparing the measured energy spectrum with the theoretical X-ray transition energy of the material. The sample composition was represented by the $K_{\alpha1}$-line (Siegbahn notations), which has the highest intensity among the characteristic X-rays of each atom. The difference between the theoretic prediction and the experimental result of K-line measurement was < 0.61% even if the characteristic X-rays from several materials were measured simultaneously. 2D images of the mixed materials were acquired with very high selectivity.

Characterization and experimental investigation for gamma-ray shielding competence of basalt-doped polyethylene nanocomposites

  • I.A. El-Mesady;F.I. El-Agawany;H. El-Samman;Y.S. Rammah;A. Hussein;R.A. Elsad
    • Nuclear Engineering and Technology
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    • 제56권2호
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    • pp.477-484
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    • 2024
  • Experimental investigations on gamma - rays attenuation parameters and dielectric spectroscopic properties were done on a polymeric mixture with chemical composition (100-x) polyethylene + x basalt, where x = 0, 1, 3, 5, 10, and 20 wt%. Using the melting blending technique,six nanocomposite polymeric samples were prepared. The linear attenuation coefficient µ of each prepared set of samples was measured using a gamma-ray spectrometer including High Purity Germanium detector (HPGe) at energies 662.5, 1173.24, and 1332.51 keV. Based on the measured values of (µ) and sample density, the other effective shielding parameters were calculated. The values of µ showed an increase with increasing the dopant ratios from 0.0 up to 20.0 wt%. In addition, the µ values decreased with the photon's energy. The µ values were found 0.0847 up to 0.1175 cm-1, 0.0571 up to 0.0855 cm-1, and 0.0543 up to 0.075 cm-1 at 662.5, 1173.24, and 1332.51 keV. for B0 up to B20, respectively. The ATR spectroscopy was done on the prepared samples, and a good evidence of adding the filler to the pure polyethylene (HDPE) was obtained. Besides, an enhancement in dielectric constant by insertion of basalt NPs also recorded and can be attributed to the large dielectric constant of basalt compared to pure HDPE.