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Tytuł artykułu

Investigation of fast neutron shielding properties of new polyurethane-based composites loaded with B4C, BeO, WO3, ZnO, and Gd2O3 micro-and nanoparticles

Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
The aim of the current research was to study the radiation shielding properties of polyurethane-based shielding materials filled with B4C, BeO, WO3, ZnO, and Gd2O3 particles against fast neutrons. The macroscopic cross sections of composites containing micro- and nanoparticles with a diameter of 10 µm and 50 nm were calculated using MCNPX (2.6.0) Monte Carlo code. The results showed that adding nano-scaled fillers to polyurethane matrix increases attenuation properties of neutron shields compared to micro-scaled fillers for intermediate and fast neutrons. Among the studied composites, WO3 and Gd2O3 nano-composites presented higher neutron cross section compared to others.
Słowa kluczowe
Rocznik
Strony
211--219
Opis fizyczny
Bibliogr. 21 poz., rys., tab.
Twórcy
  • Molecular Medicine Research Center, Institute of Biomedicine, Tabriz university of Medical Sciences, Tabriz
  • Medical Radiation Sciences Research Team, Tabriz University of Medical Sciences, Tabriz
  • Medical Radiation Sciences Research Team, Tabriz University of Medical Sciences, Tabriz
  • Department of Physics, Faculty of Basic Sciences, University of Mohaghegh Ardabili, Ardabil
  • Department of inorganic chemistry, Faculty of Chemistry, Tabriz University, Tabriz
Bibliografia
  • [1] Aghaz A, Faghihi R, Mortazavi SMJ, et al. Radiation attenuation properties of shields containing micro and Nano WO3 in diagnostic X-ray energy range. Int J Radiat Res. 2016;14(2):127-131.
  • [2] Dong Y, Chang SQ, Zhang HX, et al. Effects of WO 3 particle size in WO3/Epoxy resin radiation shielding material. Chinese Phys Letters. 2012;29(10):108102.
  • [3] Hu H, Wang Q, Qin J, et al. Study on composite material for shielding mixed neutron and gamma-rays. IEEE Trans Nucl Sci. 2008;55(4):2376-2384.
  • [4] Kim J, Seo D, Lee BC, et al. Nano-W dispersed gamma radiation shielding materials. Adv Eng Mater. 2014;16(9):1083-1089.
  • [5] Malekzadeh R, Mehnati P, Sooteh MY, Mesbahi A. Influence of the size of nano- and microparticles and photon energy on mass attenuation coefficients of bismuth-silicon shields in diagnostic radiology. Radiol Phys Technol. 2019;12(3):325-334.
  • [6] Li R, Gu Y, Wang Y, et al. Effect of particle size on gamma radiation shielding property of gadolinium oxide dispersed epoxy resin matrix composite. Mater Res Express. 2017;4(3):035035.
  • [7] Mesbahi A, Ghiasi H. Shielding properties of the ordinary concrete loaded with micro- and nano-particles against neutron and gamma radiations. Appl Radiat Isot. 2018;136:27-31.
  • [8] Mostafa AMA, Issa SAM, Sayyed MI. Gamma ray shielding properties of PbO-B2O3-P2O5 doped with WO3. J Alloys Compounds. 2017;708:294-300.
  • [9] Adeli R, Shirmardi SP, Ahmadi SJ. Neutron irradiation tests on B4C/epoxy composite for neutron shielding application and the parameters assay. Radiat Phys Chem. 2016;127:140-146.
  • [10] Tekin HO, Sayyed MI, Altunsoy EE, Manici T. Shielding properties and effects of WO3 and PbO on mass attenuation coefficients by using MCNPX code. Digest J Nanomaterials Biostructures. 2017;12(3):861-867.
  • [11] Verdipoor K, Alemi A, Mesbahi A. Photon mass attenuation coefficients of a silicon resin loaded with WO3, PbO, and Bi2O3 Micro and Nano-particles for radiation shielding. Radiat Phys Chem. 2018;147:85-90.
  • [12] Dong MG, El-Mallawany R, Sayyed MI, Tekin HO. Shielding properties of 80TeO2-5TiO2-(15-x) WO3-xAnOm glasses using WinXCom and MCNP5 code. Radiat Phys Chem. 2017;141:172-178.
  • [13] El-Mallawany R, Sayyed MI. Comparative shielding properties of some tellurite glasses: Part 1.Physica B: Condensed Matter. 2017;539:133-140.
  • [14] Noor Azman NZ, Siddiqui SA, Hart R, Low IM. Effect of particle size, filler loadings and x-ray tube voltage on the transmitted x-ray transmission in tungsten oxide-epoxy composites. Appl Radiat Isot. 2013;71(1):62-67.
  • [15] Pelowitz DB. MCNPX user's manual version (2.6.0). LA-CP-07-1473. Los Alamos National Labratory, 2008.
  • [16] Lakshminarayana G, Baki SO, Kaky KM, et al. Investigation of structural, thermal properties and shielding parameters for multicomponent borate glasses for gamma and neutron radiation shielding applications. J Non-Crystalline Solids. 2017;471:222-237.
  • [17] Noor Azman NZ, Siddiqui SA, Low IM. Characterisation of micro-sized and nano-sized tungsten oxide-epoxy composites for radiation shielding of diagnostic X-rays. Mater Sci Eng C. 2013;33(8):4952-4957.
  • [18] Sayyed MI, Elmahroug Y, Elbashir BO, Issa SAM. Gamma-ray shielding properties of zinc oxide soda lime silica glasses. J Mater Sci: Mater Electron. 2017;28:4064-4074.
  • [19] Singh K, Singh S, Dhaliwal AS, Singh G. Gamma radiation shielding analysis of lead-flyash concretes. App Radiat Isot. 2015;95:174-179.
  • [20] Tekin HO, Singh VP, Manici T. Effects of micro-sized and nano-sized WO3 on mass attenuation coefficients of concrete by using MCNPX code. Appl Radiat Isot. 2017;121:122-125.
  • [21] Tekin HO, Manici T. Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code. Nucl Sci Tech. 2017;28:95-99.
Uwagi
Opracowanie rekordu ze środków MNiSW, umowa Nr 461252 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2020).
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-f8a913c1-9a4b-4311-81a8-8a8d052cc054
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