Experimental Measurement of Infinite Dilution Thermal Neutron Self-shielding Factor

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作者
Ateia W. Mahmoud
Elsayed K. Elmaghraby
E. Salama
A. Elghazaly
S. A. El-fiki
机构
[1] Ain Shams University,Physics Department, Faculty of Science
[2] Egyptian Atomic Energy Authority,Reactor Physics Department, Nuclear Research Center
[3] Egyptian Atomic Energy Authority,Experimental Nuclear Physics Department, Nuclear Research Center
[4] The British University in Egypt (BUE),Basic Science Department, Faculty of Engineering
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Neutron self-shielding; Neutron transport and absorption; Neutron activation;
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摘要
The absorption of neutrons in media together with its transport properties cause the neutron flux to decrease as it penetrates the material because the absorption of neutrons in the sample itself attenuates the neutrons flux as it goes deeper into the sample. In the present work, the thermal neutron self-shielding factors of indium, gold, zinc, and mercury were determined experimentally. The current results together with those found in the literature were used to validate a mathematical ab initio formulae based on integral cross-section parameters used to compare our results. The complete agreement among these species of data suggests the validity of correlating the neutron migration length in the convex-shaped material with the average chord length described in the mathematical model.
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