Shielding effectiveness of boron-containing ores in Liaoning province of China against gamma rays and thermal neutrons

  • Meng-Ge Dong
  • Xiang-Xin Xue
  • V. P. Singh
  • He Yang
  • Zhe-Fu Li
  • M. I. Sayyed
Article
  • 43 Downloads

Abstract

In this study, the mass attenuation coefficient of boron-containing ores in the Liaoning province of China was calculated using WinXCOM software to investigate the shielding effectiveness of these ores against gamma rays. The mass attenuation coefficients were also calculated using MCNP-4B code and compared with WinXCOM results; consequently, a good consistency between the results of WinXCOM and MCNP-4B was observed. Furthermore, the G-P fitting method was used to evaluate the values of exposure buildup factor (EBF) in the energy range of 0.015–15 MeV up to 40 mean free paths. Among the selected ores, boron-bearing iron concentrate ore (M3) was determined to be the best gamma ray shielding ore owing to its higher values of mass attenuation coefficient and equivalent atomic number and lower value of EBF. Moreover, American Evaluated Nuclear Data File (ENDF/B-VII) was used to analyze the shielding effectiveness against thermal neutrons. It was determined that Szaibelyite (M2) is the best thermal neutron shielding material. This study would be useful for demonstrating the potential of boron-containing ores for applications in the field of nuclear engineering and technology.

Keywords

Exposure buildup factors Gamma ray Neutron Boron-containing ores G-P fitting method 

References

  1. 1.
    J. An, X.X. Xue, Life cycle environmental impact assessment of borax and boric acid production in China. J. Clean. Prod. 66, 121–127 (2014).  https://doi.org/10.1016/j.jclepro.2013.10.020 CrossRefGoogle Scholar
  2. 2.
    G. Wang, Q.G. Xue, J.S. Wang, Effect of Na2CO3 on reduction and melting separation of Ludwigite/coal composite pellet and property of boron-rich slag. Trans. Nonferrous Met. Soc. 26, 282–293 (2016).  https://doi.org/10.1016/S1003-6326(16)64116-X CrossRefGoogle Scholar
  3. 3.
    G. Wang, Y.G. Ding, J.S. Wang et al., Effect of carbon species on the reduction and melting behavior of boron-bearing iron concentrate/carbon composite pellets. Int. J. Min. Met. Mater. 20, 522–528 (2013).  https://doi.org/10.1007/s12613-013-0760-1 CrossRefGoogle Scholar
  4. 4.
    X. Ma, H. Ma, X. Jiang et al., Preparation of magnesium hydroxide nanoflowers from boron mud via anti-drop precipitation method. Mater. Res. Bull. 56, 113–118 (2014).  https://doi.org/10.1016/j.materresbull.2014.04.021 CrossRefGoogle Scholar
  5. 5.
    Z.F. Li, X.X. Xue, T. Jiang et al., Study on the properties of boron containing ores/epoxy composites for slow neutron shielding. Adv. Mater. Res. 201–203, 2767–2771 (2011).  https://doi.org/10.4028/www.scientific.net/AMR.201-203.2767 CrossRefGoogle Scholar
  6. 6.
    Z.F. Li, X.X. Xue, P.N. Duan et al., Preparation and thermal/fast neutron shielding properties of novel boron containing ore composites. Mater. Sci. Forum 743–744, 613–622 (2013).  https://doi.org/10.4028/www.scientific.net/MSF.743-744.613 CrossRefGoogle Scholar
  7. 7.
    Z.F. Li, X.X. Xue, S.L. Liu et al., Effects of boron number per unit volume on the shielding properties of composites made with boron ores from China. Nucl. Sci. Tech. 23, 344–348 (2012).  https://doi.org/10.13538/j.1001-8042/nst.23.344-348 Google Scholar
  8. 8.
    J.C. Khong, D. Daisenberger, G. Burca et al., Design and characterisation of metallic glassy alloys of high neutron shielding capability. Sci. Rep. 6, 36998 (2016).  https://doi.org/10.1038/srep36998 CrossRefGoogle Scholar
  9. 9.
    V.P. Singh, N.M. Badiger, γ-ray interaction characteristics for some boron containing materials. Vacuum 113, 24–27 (2015).  https://doi.org/10.1016/j.vacuum.2014.11.011 CrossRefGoogle Scholar
  10. 10.
    V.P. Singh, N.M. Badiger, N. Chanthima et al., Evaluation of gamma-ray exposure buildup factors and neutron shielding for bismuth borosilicate glasses. Radiat. Phys. Chem. 98, 14–21 (2014).  https://doi.org/10.1016/j.radphyschem.2013.12.029 CrossRefGoogle Scholar
  11. 11.
    M. Kurudirek, Radiation shielding and effective atomic number studies in different types of shielding concretes, lead base and non-lead base glass systems for total electron interaction: a comparative study. Nucl. Eng. Des. 280, 440–448 (2014).  https://doi.org/10.1016/j.nucengdes.2014.09.020 CrossRefGoogle Scholar
  12. 12.
    M.I. Sayyed, Bismuth modified shielding properties of zinc boro-tellurite glasses. J. Alloys Compd. 688, 111–117 (2016).  https://doi.org/10.1016/j.jallcom.2016.07.153 CrossRefGoogle Scholar
  13. 13.
    M.I. Sayyed, S.I. Quashu, Z.Y. Khattari, Radiation shielding competence of newly developed TeO2-WO3 glasses. J. Alloys Compd. (2016).  https://doi.org/10.1016/j.jallcom.2016.11.160 Google Scholar
  14. 14.
    M.I. Sayyed, Half value layer, mean free path and exposure buildup factor for tellurite glasses with different oxide compositions. J. Alloys Compd. 695, 3191–3197 (2017).  https://doi.org/10.1016/j.jallcom.2016.11.318 CrossRefGoogle Scholar
  15. 15.
    M. Kurudirek, D. Sardari, N. Khaledi et al., Investigation of X- and gamma ray photons buildup in some neutron shielding materials using GP fitting approximation. Ann. Nucl. Energy 53, 485–491 (2013).  https://doi.org/10.1016/j.anucene.2012.08.002 CrossRefGoogle Scholar
  16. 16.
    U. Fano, Gamma-ray attenuation. Part II—analysis of penetration. Minerva Med. 11, 55–61 (1953)Google Scholar
  17. 17.
    ANSI/ANS-6.4.3, Gamma ray attenuation coefficient and buildup factors for engineering materials (1991)Google Scholar
  18. 18.
    Y. Harima, Y. Sakamoto, S. Tanka et al., Validity of geometric progression formula in approximating gamma ray buildup factor. Nucl. Sci. Eng. 94, 24–25 (1986)CrossRefGoogle Scholar
  19. 19.
    Y. Harima, An historical review and current status of buildup factor calculations and application. Radiat. Phys. Chem. 41, 631–672 (1993).  https://doi.org/10.1016/0969-806X(93)90317-N CrossRefGoogle Scholar
  20. 20.
    M.B. Chadwick, M. Herman, P. Obložinský et al., ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data. Nucl. Data Sheets 112, 2887–2996 (2011).  https://doi.org/10.1016/j.nds.2011.11.002 CrossRefGoogle Scholar
  21. 21.
    G. Ilas, I.C. Gauld, G. Radulescu, Validation of new depletion capabilities and ENDF/B-VII data libraries in Scale. Ann. Nucl. Energy 46, 43–55 (2012).  https://doi.org/10.1016/j.anucene.2012.03.012 CrossRefGoogle Scholar
  22. 22.
    M.J. Berger, J.H. Hubbell, XCOM: photon cross sections database, Web Version 3.1. http://physics.nist.gov/xcom, National Institute of Standards and Technology, Gaithersburg, MD 20899, USA, 1987/99. Originally published as NBSIR 87-3597 “XCOM: Photon Cross Sections on a Personal Computer”
  23. 23.
    M.G. Dong, X.X. Xue, H. Yang et al., A novel comprehensive utilization of vanadium slag: as gamma ray shielding material. J. Hazard. Mater. 318, 751–757 (2016).  https://doi.org/10.1016/j.jhazmat.2016.06.012 CrossRefGoogle Scholar
  24. 24.
    M. Kurudirek, M. Aygun, S.Z. Erzeneoglu, Chemical composition, effective atomic number and electron density study of trommel sieve waste (TSW), Portland cement, lime, pointing and their admixtures with TSW in different proportions. App. Radiat. Isot. 68, 1006–1011 (2010).  https://doi.org/10.1016/j.apradiso.2009.12.039 CrossRefGoogle Scholar
  25. 25.
    S.M. Kulwinder, S.S. Gurdeep, Verification of some low-Z silicates as gamma-ray shielding materials. Ann. Nucl. Energy 40, 241–252 (2012).  https://doi.org/10.1016/j.anucene.2011.09.015 CrossRefGoogle Scholar
  26. 26.
    Y. Elmahroug, B. Tellili, C. Souga, Determination of total mass attenuation coefficients, effective atomic numbers and electron densities for different shielding materials. Ann. Nucl. Energy 75, 268–274 (2015).  https://doi.org/10.1016/j.anucene.2014.08.015 CrossRefGoogle Scholar
  27. 27.
    M.I. Sayyed, H. Elhouichet, Variation of energy absorption and exposure buildup factors with incident photon energy and penetration depth for boro-tellurite (B2O3–TeO2) glasses. Radiat. Phys. Chem. 130, 335–342 (2017).  https://doi.org/10.1016/j.radphyschem.2016.09.019 CrossRefGoogle Scholar
  28. 28.
    H.S. Chen, W.X. Wang, Y.L. Li et al., The design, microstructure and tensile properties of B4C particulate reinforced 6061Al neutron absorber composites. J. Alloys Compd. 632, 23–29 (2015).  https://doi.org/10.1016/j.jallcom.2015.01.048632:23-29 CrossRefGoogle Scholar
  29. 29.
    V.F. Sears, Neutron scattering lengths and cross sections. Neutron News. 3, 26–37 (2006).  https://doi.org/10.1080/10448639208218770 CrossRefGoogle Scholar
  30. 30.
    T. Özdemir, İ.K. Akbay, H. Uzun et al., Neutron shielding of EPDM rubber with boric acid: mechanical, thermal properties and neutron absorption tests. Prog. Nucl. Energy 89, 102–109 (2016).  https://doi.org/10.1016/j.pnucene.2016.02.007 CrossRefGoogle Scholar

Copyright information

© Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Chinese Nuclear Society, Science Press China and Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  • Meng-Ge Dong
    • 1
  • Xiang-Xin Xue
    • 1
  • V. P. Singh
    • 2
  • He Yang
    • 1
  • Zhe-Fu Li
    • 3
  • M. I. Sayyed
    • 4
  1. 1.Department of Resource and Environment, School of MetallurgyNortheastern UniversityShenyangChina
  2. 2.Department of PhysicsKarnatak UniversityDharwadIndia
  3. 3.Shanghai Institute of Applied PhysicsShanghaiChina
  4. 4.Physics DepartmentUniversity of TabukTabukSaudi Arabia

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