The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite

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Communications Faculty of Sciences University Ankara Series A1 Mathematics and Statistics
Volume:22
The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite

The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite

Authors : E ERDİK

Pages : 0-0

Doi:10.1501/Commua1_0000000627

View : 22 | Download : 9

Publication Date : 1973-01-01

Article Type : Research Paper

Abstract :The experimental determination of the thermal neutron diffusion length in gra- phite was carried out by measuring the distribution of neutron fiux along the x, y, and z axis. The neutron flux distribution have been measured with a BF,3 counter using a Ra - Be neutron source. For the calculation of the results the least sguares method was chosen in order to obtain the most probable value of the diffusîon length. The value of the diffusion length was found to be L = 58 i 2 cm for the Diffusi- on Stack and L — 53,46 cm insert ignore into journalissuearticles values(average); for the Exponential Stack.
Keywords : Experimental Determination, Thermal Neutron, Graphite

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