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Fabrication and Radiocharacterization of Boron Carbide and Tungsten Incorporated Rubber Shields

Journal Name:

  • International Journal of Innovation and Applied Studies

Publication Year:

  • 2013

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Abstract (Original Language): 
Radioactive ray safeguard is a physical impediment which is placed between radioactive source and the protected object in order to decrease the amount of rays' radiation in the protected area. Different materials such as lead, iron, graphite, water, poly ethylene, concrete, or rubber can be used for protection against nuclear radiations. In safeguard's common designing, two types of Gama and Neutron radiations are usually considered. The weakening amount of Gama radiations is proportional to the mass and atomic number of the safeguard's material. Covering Neutron source varies with regard to the source power and its application. However, what is always true is having the least dose with the least dimensions outside the safeguard. The dose of the safeguard's outside partition is resulted from quick, slow and thermal neutrons, and also from the source's Gammas and secondary Gammas. Neutrons use retarding and neutron-absorbing materials in order to reduce the dose. Due to the weak mechanical characteristics of the pure elastic composites, fillers are used to strengthen and improve their characteristics. Strengthening the elastic material is often defined through increasing the characteristics such as hardness, module, refraction energy, solidity, tear resistance, tensile solidity, lassitude resistance, abrasion resistance. In this paper, rubber shielding materials with boron carbide and tungsten as impurities have been fabricated. The optimum boron carbide contents (5% weight percent) have been evaluated using the Monte Carlo code, MCNP. The gamma attenuation coefficients for different boron carbide and tungsten contents have been measured for a number of rubber shields with dimensions of 1×9×16cm3.
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REFERENCES

References: 

[1] K., Heydari, N., and S. Ashrafi, “Management of agricultural water consumption, drought, and supply of water for future
demand in Iran,” Proceedings of 7th Int’l Conference on Sustainable Development and Management of Dry-lands in 21
century, 2003.
[2] United Nations, The Demand for water: Procedures and methodologies for projecting water demands in the context of
regional national planning, Nat. Resource, Water Ser. 3, United Nations Publications, New York, 2007.
[3] World Energy Council (WEC), Energy Efficiency Policies around the World: Review and Evaluation Executive Summary, A
Report by the Word Energy Council, London, United Kingdom, 2008.
[4] Interlined M.A., et al., Integrated Evaluation of Energy Conservation, National Report for the Netherlands, Energy
Research Center of the Netherlands, 1999.
[5] Anderson J., “The environmental benefits of water recycling and reuse,” Water Science and Technology, 2006.
[6] Metcalf & Eddy, Water Reuse, Issues, Technology and Application, McGraw-Hill, 2007.
[7] Herbert Son, P.W. and E.L. Tate, “Tools for water use and demand management in South Africa, World Meteorological
Organization,” Technical Reports in Hydrology and Water Resources, 2007.
[8] Aprsht, W, “identification of structural materials in nuclear technology,” refugees, H, printing, Tehran, Tehran University
Institute for Publishing and Print, 2009.
[9] ACI Committee 211, Standard Practice for Selecting Proportions for Normal, Heavy weight, and Mass Concrete,
Appendix (4), American Concrete Institute, 2002.
[10] ACI Committee 304, Heavyweight concrete, Measuring, Mixing, transporting, and, Placing (ACI 304.3R-96), Detroit,
American Concrete Institute,1996.
[11] 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.
[12] Bashter, I. I., “Calculation of radiation attenuation coefficients for shielding concretes,” Annals of Nuclear Energy,
Volume 24, Issue 17, pp. 1389-1401, 1997.

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