Volume 4, Issue 2, October 2013, Pages 437–440
Marzieh Salimi1, Eskandar Asadi Amirabadi2, Nima Ghal-Eh3, Zahra Soltani4, and Gholam Reza Etaati5
1 School of Physics, Damghan University, Damghan, Iran
2 Department of Physics, Payam-e-Noor University, Tehran, Iran
3 School of Physics, Damghan University, Damghan, Iran
4 Energy Engineering and Physics Department, Amir Kabir University of Technology, Tehran, Iran
5 Energy Engineering and Physics Department, Amir Kabir University of Technology, Tehran, Iran
Original language: English
Copyright © 2013 ISSR Journals. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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
Author Keywords: Rubber Shielding, Boron Carbide, Tungsten, Gamma Attenuation, MCNP.
Marzieh Salimi1, Eskandar Asadi Amirabadi2, Nima Ghal-Eh3, Zahra Soltani4, and Gholam Reza Etaati5
1 School of Physics, Damghan University, Damghan, Iran
2 Department of Physics, Payam-e-Noor University, Tehran, Iran
3 School of Physics, Damghan University, Damghan, Iran
4 Energy Engineering and Physics Department, Amir Kabir University of Technology, Tehran, Iran
5 Energy Engineering and Physics Department, Amir Kabir University of Technology, Tehran, Iran
Original language: English
Copyright © 2013 ISSR Journals. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
Abstract
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
Author Keywords: Rubber Shielding, Boron Carbide, Tungsten, Gamma Attenuation, MCNP.
How to Cite this Article
Marzieh Salimi, Eskandar Asadi Amirabadi, Nima Ghal-Eh, Zahra Soltani, and Gholam Reza Etaati, “Fabrication and Radiocharacterization of Boron Carbide and Tungsten Incorporated Rubber Shields,” International Journal of Innovation and Applied Studies, vol. 4, no. 2, pp. 437–440, October 2013.
