Buradasınız

Anasayfa » Content

Study of Neutron and Gamma Radiation Protective Shield

Journal Name:

  • International Journal of Innovation and Applied Studies

Publication Year:

  • 2013

Key Words:

Author NameUniversity of Author
Abstract (2. Language): 
Due to the development of nuclear technology and use of these technologies in various fields of industry, medicine, research and etc, protection against radioactive rays is one of the most important topics in this field .The purpose of this is to reduce the dose rate from radioactive sources. The sources in terms of components are emitted various types of nuclear radiation with different energies. These radiations are involving of alpha particles, beta, and neutron and gamma radiation. Given that alpha and beta particles can be fully absorbed by the shield, the main issue in the debate protection radioactive rays is stopping of gamma rays and neutrons. Accordingly in shield design usually two types of radiation should be considered. First, X-rays and gamma rays, which have great influence, and by the mass of any suitable material, can be more efficiently attenuate the higher the density, the better the potential attenuation effect against gamma rays and the required shielding thickness decreases. The second type of radiation is neutrons. Often a combination of three materials is desirable that include heavy metals, light metals, and neutron-absorbing material to omit the slow neutrons through adsorption to the neutron shield. There are different materials that can be used to shielding against radioactive rays. The main materials that are used in protection include: water, lead, graphite, iron, compounds that contains B, concrete, and polyethylene. Accordingly, the main objective of this paper is evaluating the kind of shield against gamma and neutrons rays.
Bookmark/Search this post with
FULL TEXT (PDF): 
PDF icon ijias-13-156-06.pdf
  • 4
1079-1085
  • English

REFERENCES

References: 

[1] Aprsht, W., “identification of structural materials in nuclear technology”, refugees, H, printing, Tehran, Tehran
University Institute for Publishing and Print, 2009.
[2] ACI Committee 211, “Standard Practice for Selecting Proportions for Normal, Heavy weight, and Mass Concrete”,
Appendix 4, American Concrete Institute, 2002.
[3] ACI Committee 304, “Heavyweight concrete, Measuring, Mixing, transporting, and, Placing (ACI 304.3R-96)”, Detroit,
American Concrete Institute, 1996.
[4] Akkurt, I, et al., “Radiation shielding of concretes containing differed aggregates”, Cement and Concrete Composites,
Vol. 28, no. 2, 2006.
[5] American Society for Testing and Materials, “Annual Book of ASTh Standards, Significance of tests and properties of
concrete an concrete making materials,” United States, ASTM special Technical Publication, Vol. 04.01, 04.02, 2007.
[6] Bashter, I. I., “Calculation of radiation attenuation coefficients for shielding concretes”, Annals of Nuclear Energy, Vol.
24, no. 17, pp. 1389-1401, 1997.
[7] Basyigit, C. et al., “The effect of freezing-thawing (FT) cycles on the radiation shielding properties of concretes”, Building
and Environment, Vol. 41, no. 8, pp. 1070-1073, 2009.
[8] Chilton, A. B., Shultis., J.K., and Few, R. E., “Principles of Radiation Shielding”, Prentice-Hall, Englewood Cliffs, NJ 07632,
1984.
[9] RG Jaeger, Engineering Compendium on Radiation Shielding, Springer-Verlag, New York, USA, 1968.
[10] Sakr, K, et al., “Effect of high temperature or fire on heavy weight concrete properties”, Cement and Concrete Research,
Vol. 35, no. 3, pp. 590-596, 2005.
[11] Suzuki, A, et al., “Trace Elements with Large Activation Cross Section in Concrete Materials in Japan”, Journal of Nuclear
Science and Technology, Vol. 38, No. 7, pp. 542-550, 2001.

Thank you for copying data from http://www.arastirmax.com