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Gamma-ray absorption using rubber—lead mixtures as radiation protection shields

  • Ahmed Khalaf Mheemeed
  • Hana Ihsan Hasan
  • Firas Mohammed Al-Jomaily
Article

Abstract

In the present study five samples of special rubber–lead were fabricated each of them consists of lead and rubber with different weight ratios. The fabrication was carried out through the process of mixing under compression pressure. Gamma-ray transmission method was employed to determine the linear attenuation coefficient for narrow collimated mono-energetic beams of gamma-rays emitted from 241Am 0.059, 152Eu 0.13 and 137Cs 0.662 MeV. The linear attenuation coefficient of standard rubber–lead shield was also experimentally determined. The percentage of lead in standard rubber–lead shield was determined through the calibration curve or by a simple computer program written in MATLAB. All prepared samples are characterized as flexible and gives a good homogeneity. samples no. 4 & 5 offers the best performance as a radiation protection shields. The results showed an inverse proportionality between the linear attenuation coefficient μl and E, and μl has a direct proportionality with mixing ratios (sample density). The results showed an inverse proportional between the half value layers and the average linear attenuation coefficients of the various samples.

Keywords

NBR Radiation shielding Gamma-ray Attenuation coefficient Homogeneity 

References

  1. 1.
    Krane K (1987) Introductory nuclear physics. Wiley, New YorkGoogle Scholar
  2. 2.
    Johns and Cunningham (1978) The Physics of Radiology, 3rd edn.Google Scholar
  3. 3.
    Lamarch J (1975) Introduction to nuclear engineering. Addison-Wesley, MassachusettsGoogle Scholar
  4. 4.
    Shapiro J (1982) Radiation protection: a guide for scientists and physicians, 2nd edn.Google Scholar
  5. 5.
    Hill A (1999) Half value layer measurements to facilitate patient dose assessment for newer CT scanners using published normalized dose data. Br J Radiol 72(860):792–798Google Scholar
  6. 6.
    Hussain R, Haq Z, Mohammad D (1997) A study of the shielding properties of poly ethylene glycol-lead oxide composite. J Islamic Acad Sci 10(3):81–84Google Scholar
  7. 7.
    Fuga P (1990) Removal cross sections for 14.6 MeV neutrons. J Radioanal Nucl Chem 149(2):287–290Google Scholar
  8. 8.
    Braoudakis G et al (1998) Nucl Instrum Methods 403:449–460Google Scholar
  9. 9.
    Murbut A, Namah A, Taki A (2000) Measurement of gamma-ray attenuation in compressed soil sample. Sci J Iraqi At Energy Comm 2(2):46–52Google Scholar
  10. 10.
    Friedman HW, Singh MS and DeMeo RF (2003) radiation transmission measurements for a lightweight fabric. American Nuclear Society Annual Meeting, San Diego, JCRL-JC-151233Google Scholar
  11. 11.
    Gally J, Berthonu V, Magill J (2004) Γ-Dose: auser-friendly module for dosimetry and shielding calculations, Maderia,9_14 May 2004-21 Century challenges in Radiation protection and shielding ICRSLO-RPSGoogle Scholar
  12. 12.
    Fathi F (2005) Mass attenuation of gamma photons in special lead glass that can be used in radiation shielding windows. Raf J Sci 17(2):130–138Google Scholar
  13. 13.
    Jameel H, Al-dayel O, Al-horayess O, Al-ajyan T (2010) Gamma ray shielding from white sand. Energy Power Eng 2(1):6–9. http://www.scirp.org/journal/epe Google Scholar
  14. 14.
    El-khayatt A (2011) NXcom-aprogram for calculating attenuation coefficients of fast neutron and gamma-rays. Ann Nucl Energy 38:128–132CrossRefGoogle Scholar
  15. 15.
    Wafa A, Siham A (2005) Using beta-particle for measuring the homogeneity of rubber compound and studying the effect of compression, temperature and pressure on its homogeneityand mechanical properties. Raf J Sci 16(1):115–120Google Scholar
  16. 16.
    Mahrok M, Sleeman S (2002) The importance of collimator in the measurement of sample thickness by gamma ray. Raf J Sci 3(13):124Google Scholar
  17. 17.
    Lilley J (2001) Nuclear physics principles and application. Wiley, University of Manchester, New YorkGoogle Scholar
  18. 18.
    Al-Ahmed KO (1993) Introduction of health physics. Dar-Al Ktub for printing and Publishing University of Mosul. Press Mosul University, MosulGoogle Scholar
  19. 19.
    El-Sersy A, Hussein A, El-semman H, El-adawy A, Donya H (2011) Mass attenuation coefficient of B2O3–Al2O3–SiO2–CaF2 glass system at o.662 and 1.25 MeV gamma energies. J Radioanal Nucl Chem 288:65–69CrossRefGoogle Scholar
  20. 20.
    Suparat T, Jakrapong K, Pichet L, Weerapong C (2011) Development of BaO:B2O3:flyash glass system for gamma-rays shielding materials. Nucl Sci Technol 1:110–113Google Scholar
  21. 21.
    Stankovic S, Ilic R, Jankovic K, Bojovic D, Loncar B (2010) Gamma radiation absorption characteristics of concrete with compound type materials. Acta Phys Polonica A 117(5):812–816Google Scholar
  22. 22.
    El-Taher A (2007) Comparative study of attenuation and scattering of gamma-rays through two intermediate rocks. Indian J Pure Appl Phys 45:198–203Google Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2011

Authors and Affiliations

  • Ahmed Khalaf Mheemeed
    • 1
  • Hana Ihsan Hasan
    • 1
  • Firas Mohammed Al-Jomaily
    • 2
  1. 1.Physics Department, Education CollegeMosul UniversityMosulIraq
  2. 2.Physics Department, Science CollegeMosul UniversityMosulIraq

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