Volume 3, Issue 2 (6-2015)                   IJRSM 2015, 3(2): 1-6 | Back to browse issues page

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rezaee ebrahim saraee K, Tajeri A, Pourajam Baferani S, Jabbari I. The feasibility of a shield for the 241Am-9Be source using industrial wastes by experimental methods and genetic algorithm. IJRSM. 2015; 3 (2) :1-6
URL: http://rsm.kashanu.ac.ir/article-1-113-en.html
University of Isfahan
Abstract:   (9775 Views)

In this study, a mixture of waste lead mine Nakhlak and cement with different percentages of boric acid are used to construct a proper shield for gamma and neutron radiations emitted from the Am-Be source. Neutron dose rate reduction ​​by the prepared samples was investigated by thermal neutron irradiation system of Isfahan University, TLD 600 and TLD 700. Neutron dose rate changes, compressive strength and sample activation induced by the neutron irradiation were measured. The effect of various amounts of boric acid in the prepared shield on total mass attenuation coefficient of gamma radiation was investigated by WINXCOM software. Using genetic algorithm, the optimum amounts of boric acid and neutron dose rate were calculated 53.15% and 90.1% respectively. Also, for the shield with the optimum amount of boric acid, total mass attenuation coefficient for 4.438 MeV gamma radiation and compressive strength were obtained 0.03262 cm2/g and 120.36 Kg/cm2 respectively.

Type of Study: Research | Subject: Special

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