Average neutron Cross-Section of 27 al using 241 AM/BE neutron source
DOI:
https://doi.org/10.69844/wnj16607Keywords:
Moderation, cross-section, neutron, sourceAbstract
#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.