Average neutron Cross-Section of 27 al using 241 AM/BE neutron source

Authors

  • Abdullah Ahmed Al-Shamy Author

DOI:

https://doi.org/10.69844/wnj16607

Keywords:

Moderation, cross-section, neutron, source

Abstract

#This research aims to study the average cross-section of neutron AL 27 using the neutron source Be/Am 241. The research followed an experimental methodology and consisted of an introduction, three sections, and a conclusion. The introduction discussed the importance and theoretical framework of the study. The first section focused on the experimental procedure and the calculation of neutron cross-sections using the official numerical method.  The second section involved finding the theoretical values of these cross-sections using the codes SCAT2000 for calculating the total and elastic cross-sections and the code CINDY for calculating the cross-section *'Al(n,p) 'Mg.  The third section presented and discussed the results.  The conclusion summarized the key findings, including that the measured average value is 25 + 0.48 megabarns, which is consistent with the calculated values.

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Published

30-12-2007

How to Cite

Average neutron Cross-Section of 27 al using 241 AM/BE neutron source. (2007). The University Researcher Journal of Human Sciences, 9(14). https://doi.org/10.69844/wnj16607