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    Wyświetlanie 1-3 z 3
    Tytuł:
    Prompt gamma-ray methods for industrial process evaluation : a simulation study
    Autorzy:
    Mohammed, Mohammed Siddig H.
    Alhawsawi, Abdulsalam M.
    Aljohani, M. S.
    Damoom, Mohammed M.
    Banoqitah, Essam M.
    Elmoujarkach, Ezzat
    Powiązania:
    https://bibliotekanauki.pl/articles/2105331.pdf
    Data publikacji:
    2022
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    prompt gamma ray
    sealed sources
    radiotracers
    industrial process
    Opis:
    Radioisotope applications in industrial process inspection and evaluation using gamma-ray emitters provide otherwise unavailable information. Offering alternative gamma-ray sources can support the technology by complementing sources’ availability and radiation safety. This work proposes to replace gamma-ray from radioisotopes with prompt gamma-ray from the interaction of neutrons with stable isotopes injected into the industrial process or with the structural material of the industrial process equipment. Monte Carlo N-Particle Transport Code (MCNP5) was used to simulate the irradiation of two-phase fl ow pipes by 252Cf neutron source. Two simulations were run for each pipe, with and without mixing the liquid phase with the stable isotope 157Gd. The detected gamma-ray spectra were analysed, and images of the two phases inside the pipes were produced. The images were compared to images obtained from simulations of gamma transmission measurement using 60Co. Furthermore, results for prompt gamma computed tomography (CT) were presented and discussed. The studies’ outcomes indicate the potential of prompt gamma-ray to carry out the sealed sources applications of gamma transmission measurements and imaging.
    Źródło:
    Nukleonika; 2022, 67, 1; 11--18
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Fluka simulation of PGNAA system for determining heavy metal pollution in the soil sample
    Autorzy:
    Zhang, Can
    Yang, Jianbo
    Li, Rui
    Qiao, Yujie
    Zhang, Xu
    Xu, Jie
    Powiązania:
    https://bibliotekanauki.pl/articles/146960.pdf
    Data publikacji:
    2020
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    PGNAA
    Fluka
    heavy metal
    prompt gamma-ray yield
    metal ciężki
    szybka wydajność
    promieniowanie gamma
    Opis:
    This study presented a self-designed prompt gamma neutron activation analysis (PGNAA) model and used Fluka simulation to simulate the heavy metals (Mn, Cu, Hg, Ni, Cr, Pb) in soil samples. The relationship between the prompt gamma-ray yield of each heavy metal and soil thickness, content of heavy metals in the soil, and source distance was obtained. Simulation results show that the prompt gamma-ray yield of each heavy metal increases with the increase in soil thickness and reaches saturation at 18 cm. The greater the proportion of heavy metals in the soil, the greater the prompt gamma-ray yield. The highest content is approximately 3%, and the change in distance between the neutron source and soil sample does not affect the prompt gamma-ray yield of heavy metals.
    Źródło:
    Nukleonika; 2020, 65, 1; 13-17
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Investigation of thermal neutron detection capability of a CdZnTe detector in a mixed gamma-neutron radiation field
    Autorzy:
    Yücel, H.
    Narttürk, R. B.
    Zümrüt, S.
    Gedik, G.
    Karadag, M.
    Powiązania:
    https://bibliotekanauki.pl/articles/146914.pdf
    Data publikacji:
    2018
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    neutron detection
    CdZnTe
    prompt gamma ray
    thermal neutron
    cadmium
    neutron sensitivity
    241Am-Be source
    Opis:
    The aim of this study was to investigate the thermal neutron measurement capability of a CdZnTe detector irradiated in a mixed gamma-neutron radiation fi eld. A CdZnTe detector was irradiated in one of the irradiation tubes of a 241Am-Be source unit to determine the sensitivity factors of the detector in terms of peak count rate (counts per second [cps]) per neutron flux (in square centimeters per second) [cps/neutron•cm–2•s–1]. The CdZnTe detector was covered in a 1-mm-thick cadmium (Cd) cylindrical box to completely absorb incoming thermal neutrons via 113Cd(n,γ) capture reactions. To achieve, this Cd-covered CdZnTe detector was placed in a well-thermalized neutron fi eld (f-ratio = 50.9 ± 1.3) in the irradiation tube of the 241Am-Be neutron source. The gamma-ray spectra were acquired, and the most intense gamma-ray peak at 558 keV (0.74 γ/n) was evaluated to estimate the thermal neutron fl ux. The epithermal component was also estimated from the bare CdZnTe detector irradiation because the epithermal neutron cutoff energy is about 0.55 eV at the 1-mm-thick Cd filter. A high-density polyethylene moderating cylinder box can also be fi tted into the Cd fi lter box to enhance thermal sensitivity because of moderation of the epithermal neutron component. Neutron detection sensitivity was determined from the measured count rates from the 558 keV photopeak, using the measured neutron fluxes at different irradiation positions. The results indicate that the CdZnTe detector can serve as a neutron detector in mixed gamma-neutron radiation fields, such as reactors, neutron generators, linear accelerators, and isotopic neutron sources. New thermal neutron filters, such as Gd and Tb foils, can be tested instead of the Cd filter due to its serious gamma-shielding effect.
    Źródło:
    Nukleonika; 2018, 63, 3; 59-64
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-3 z 3

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