SHIELDING ELECTRONIC CIRCUITS FROM SPACE-NEUTRONS AND CAPTURE GAMMA-RAYS | ||||
| Bulletin of Faculty of Science, Zagazig University | ||||
| Article 5, Volume 2019, Issue 1, December 2019, Page 48-53 PDF (409.65 K) | ||||
| Document Type: Original Article | ||||
 View on SCiNiTO | ||||
| Authors | ||||
| EzzEldin Korkom1; Moustafa Aziz2; S. S. Mustafa3; Ibrahim Bashter* 3 | ||||
| 1Physics Department, Faculty of Science, Zagazig University, Egypt Faculty of Science, Dr John Garang University, Bor –Jonglei State , South Sudan | ||||
| 2Nuclear and Radiological Regulatory Authority, Cairo, Egypt | ||||
| 3Physics Department, Faculty of Science, Zagazig University, Egypt | ||||
| Abstract | ||||
| This work study the shielding effectiveness of polyethylene, polyethylene loaded with both boron (5% & 10% Boron) and lithium (7.5% lithium), aluminum and multilayer shield composed of aluminum and polyethylene loaded lithium against space-neutrons and neutron induced gamma rays to protect electronic circuits against space-neutrons and capture gamma-rays. MCNP5 code was used to analyze the shield thickness required to attenuate 14 MeV neutrons and secondary photons that produced from the interaction of fast neutrons with these materials. Effective attenuations for all sample materials have been calculated. No significant attenuation effect of adding boron to polyethylenedue to its low absorption cross section at high neutron energy. It was found that the multilayer shield is the best material to attenuate fluxes and doses of neutrons and gamma rays.This shield can attenuate neutron flux up to 99.62%, neutron dose to 99.73%, gamma flux to 96.90% and gamma dose to 97.97%. | ||||
| Keywords | ||||
| Shielding materials Space Neutron Capture Gamma; Rays MCNP5 code Simulation Calculation | ||||
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