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Year 1973, Volume: 22 , 0 - 0, 01.01.1973

E. Erdik

https://doi.org/10.1501/Commua1_0000000627

Abstract

References

  • Ankara Üniversitesi – Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics Dergisi

The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite

Year 1973, Volume: 22 , 0 - 0, 01.01.1973

E. Erdik

https://doi.org/10.1501/Commua1_0000000627

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 (average) for the Exponential Stack.

Keywords

Experimental Determination Thermal Neutron Graphite

References

  • Ankara Üniversitesi – Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics Dergisi
There are 1 citations in total.

Details

Primary Language English
Subjects Mathematical Sciences
Journal Section Research Articles
Authors

E. Erdik This is me

Publication Date January 1, 1973
Submission Date January 1, 1973
Published in Issue Year 1973 Volume: 22

Cite

APA Erdik, E. (1973). The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite. Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics, 22. https://doi.org/10.1501/Commua1_0000000627
AMA Erdik E. The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite. Commun. Fac. Sci. Univ. Ank. Ser. A1 Math. Stat. January 1973;22. doi:10.1501/Commua1_0000000627
Chicago Erdik, E. “The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite”. Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics 22, January (January 1973). https://doi.org/10.1501/Commua1_0000000627.
EndNote Erdik E (January 1, 1973) The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite. Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics 22
IEEE E. Erdik, “The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite”, Commun. Fac. Sci. Univ. Ank. Ser. A1 Math. Stat., vol. 22, 1973, doi: 10.1501/Commua1_0000000627.
ISNAD Erdik, E. “The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite”. Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics 22 (January 1973). https://doi.org/10.1501/Commua1_0000000627.
JAMA Erdik E. The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite. Commun. Fac. Sci. Univ. Ank. Ser. A1 Math. Stat. 1973;22. doi:10.1501/Commua1_0000000627.
MLA Erdik, E. “The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite”. Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics, vol. 22, 1973, doi:10.1501/Commua1_0000000627.
Vancouver Erdik E. The Experimental Determination of the Thermal Neutron Diffusion Length in Graphite. Commun. Fac. Sci. Univ. Ank. Ser. A1 Math. Stat. 1973;22.

Communications Faculty of Sciences University of Ankara Series A1 Mathematics and Statistics.

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