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A Study of Gamma Unfolding for PB, HC Single Shields and Multilayers Containing PB Shield

Received: 29 December 2016     Accepted: 10 April 2017     Published: 15 January 2018
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Abstract

The gamma ray spectrum obtained from a 3.7 × 104 Bq 252Cf source after passing through different shielding materials at different thicknesses and different arrangements were detected with a NaI(Tl) detector was fed to a computerized MCA to have a spectrum. This was then stored and subsequently unfolded. The unfolded dose spectra of the fission gamma ray spectrum of the 252Cf source were also measured for some specific shield thicknesses for all the shielding arrangements studied. Theoretical calculations have been performed to study the characteristics of the above mentioned shielding setups by using the three dimensional Monte Carlo computer code MCNP for fission gamma rays. These are then compared with the experimentally obtained values. The agreement is quite satisfactory. Gamma ray fluxes and corresponding dose values have also been calculated. The purpose of the investigation was to determine the effectiveness of the materials and their multilayers as the gamma ray shielding. It has been found that the materials (single layer and multilayer) studied are very effective as the shield for gamma rays.

Published in American Journal of Physical Chemistry (Volume 6, Issue 6)
DOI 10.11648/j.ajpc.20170606.12
Page(s) 110-118
Creative Commons

This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.

Copyright

Copyright © The Author(s), 2018. Published by Science Publishing Group

Keywords

Gamma Unfolding, PB (Poly Boron), HC (Heavy Concrete), PB Single Shields, Multilayers, Monte Carlo Computer Code MCNP, Fission Gamma Rays

References
[1] Neutron Gamma Shielding, Reactor Experiments, Inc. USA Catalogue 24, p 2.
[2] F. E. Senetle and P. Philbin, Health Phys., 23(1972)529-532.
[3] R. M. Megahid, Int. Jr. Appl. Radiat. Isot. 36(1985)307-310.
[4] M S Hossain, S. M. A. Islam, M. Asaduzzaman, and M. A. Zaman, A Study of Gamma Unfolding for PB, BX Single Shields and Multilayers Containing PB Shield, NUB Journal of applied Sciences, Vol -3, Issue- 1, May 2016.
[5] M S Hossain, M. A. Quasem, S. M. A. Islam and M. A. Zaman Study of shielding behaviour of some multilayer shields containing PB and BX, Journal of Applied Physics, India, 2010.
[6] G. F. Knoll, Radiation Detection and Measurements, 1979, John Wiley and Sons, Inc. p 732.
[7] J. H. Hubble, Rev. Sci. Instr. 29(1958)65.
[8] R. Gold, TID, 18304(1963).
[9] C. A. Bisselle, R. A. Karam and J. A. Wethington JR., University of Florida, Gainesville, Fia. Appl. Radiat. Isot., 5(1964)529-539.
[10] Edgardo Browne and Richard B. Firestone, “Table of Radoactive Isotopes”, Virginia S. Shirley, Editor, A Wiley-Interscience Publication, John Wiley & Sons, USA (1986), ISBN O-471-84909-X.
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  • APA Style

    M. S. Hossain, S. M. A. Islam, M. Asaduzzaman, M. A. Zaman. (2018). A Study of Gamma Unfolding for PB, HC Single Shields and Multilayers Containing PB Shield. American Journal of Physical Chemistry, 6(6), 110-118. https://doi.org/10.11648/j.ajpc.20170606.12

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    ACS Style

    M. S. Hossain; S. M. A. Islam; M. Asaduzzaman; M. A. Zaman. A Study of Gamma Unfolding for PB, HC Single Shields and Multilayers Containing PB Shield. Am. J. Phys. Chem. 2018, 6(6), 110-118. doi: 10.11648/j.ajpc.20170606.12

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    AMA Style

    M. S. Hossain, S. M. A. Islam, M. Asaduzzaman, M. A. Zaman. A Study of Gamma Unfolding for PB, HC Single Shields and Multilayers Containing PB Shield. Am J Phys Chem. 2018;6(6):110-118. doi: 10.11648/j.ajpc.20170606.12

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  • @article{10.11648/j.ajpc.20170606.12,
      author = {M. S. Hossain and S. M. A. Islam and M. Asaduzzaman and M. A. Zaman},
      title = {A Study of Gamma Unfolding for PB, HC Single Shields and Multilayers Containing PB Shield},
      journal = {American Journal of Physical Chemistry},
      volume = {6},
      number = {6},
      pages = {110-118},
      doi = {10.11648/j.ajpc.20170606.12},
      url = {https://doi.org/10.11648/j.ajpc.20170606.12},
      eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ajpc.20170606.12},
      abstract = {The gamma ray spectrum obtained from a 3.7 × 104 Bq 252Cf source after passing through different shielding materials at different thicknesses and different arrangements were detected with a NaI(Tl) detector was fed to a computerized MCA to have a spectrum. This was then stored and subsequently unfolded. The unfolded dose spectra of the fission gamma ray spectrum of the 252Cf source were also measured for some specific shield thicknesses for all the shielding arrangements studied. Theoretical calculations have been performed to study the characteristics of the above mentioned shielding setups by using the three dimensional Monte Carlo computer code MCNP for fission gamma rays. These are then compared with the experimentally obtained values. The agreement is quite satisfactory. Gamma ray fluxes and corresponding dose values have also been calculated. The purpose of the investigation was to determine the effectiveness of the materials and their multilayers as the gamma ray shielding. It has been found that the materials (single layer and multilayer) studied are very effective as the shield for gamma rays.},
     year = {2018}
    }
    

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    AU  - M. S. Hossain
    AU  - S. M. A. Islam
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    T2  - American Journal of Physical Chemistry
    JF  - American Journal of Physical Chemistry
    JO  - American Journal of Physical Chemistry
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    EP  - 118
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    AB  - The gamma ray spectrum obtained from a 3.7 × 104 Bq 252Cf source after passing through different shielding materials at different thicknesses and different arrangements were detected with a NaI(Tl) detector was fed to a computerized MCA to have a spectrum. This was then stored and subsequently unfolded. The unfolded dose spectra of the fission gamma ray spectrum of the 252Cf source were also measured for some specific shield thicknesses for all the shielding arrangements studied. Theoretical calculations have been performed to study the characteristics of the above mentioned shielding setups by using the three dimensional Monte Carlo computer code MCNP for fission gamma rays. These are then compared with the experimentally obtained values. The agreement is quite satisfactory. Gamma ray fluxes and corresponding dose values have also been calculated. The purpose of the investigation was to determine the effectiveness of the materials and their multilayers as the gamma ray shielding. It has been found that the materials (single layer and multilayer) studied are very effective as the shield for gamma rays.
    VL  - 6
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Author Information
  • Dept. of Physics, Bangladesh Army University of Engineering & Technology (BAUET), Qadirabad Cantonment, Natore, Bangladesh

  • Dept. of Physics, Jahangirnagar University, Savar, Dhaka, Bangladesh

  • Dept. of Physics, Bangladesh Army University of Engineering & Technology (BAUET), Qadirabad Cantonment, Natore, Bangladesh

  • Dept. of Physics, Jahangirnagar University, Savar, Dhaka, Bangladesh

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