@article { author = {Hammody, Faissal and Hady, Firas and Muwafaq, Omar.}, title = {}, journal = {Journal of Garmian University}, volume = {5}, number = {2}, pages = {282-293}, year = {2018}, publisher = {University of Garmian}, issn = {23100087}, eissn = {25223879}, doi = {10.24271/garmian.343}, abstract = {}, keywords = {}, title_ku = {Measurement of the Average Cross-Section Values for Neutron Reaction with the Elements (Mg , Al, Fe, Ni, Zn , Cu) from the Neutron Source 241 Am/Be.}, abstract_ku = {The average cross- section for fast neutron reactions with the elements (Mg , Al, Fe,Ni, Zn , Cu) in 65 Cu(n, p) 65 Ni, 64 Zn(n, p) 64 Cu, 58 Ni(n, p) 58 Co, 56 Fe(n, p) 56 Mn, 57 Al(n,p) 57 Mg and 24 Mg(n, p) 24 Na reactions has been calculated by using the numerical –graphical method for 241 Am/Be neutron source according to the intensity distributionof the source as a function of neutron energy. The corresponding neutron cross-section values at certain energies are taken from neutron cross-sections curves.Furthermore, the average neutron cross-sections for each of these reactions have beenmeasured using the activation method. A well-type NaI(Tℓ) detector was used formeasuring the radiation activity.The cross-sections for these reaction were measured by using of 27 Al(n, p) 27 Mgreaction as a reference for short-lived activity arising in the different reactions. Forlong - lived activities the 27 Al(n, ) 24 Na, and 56 Fe (n, p) 56 Mn are used. It is found thatthe cross – section for the 65 Cu isotope is σ =826.29±62 mb while the standard valueis σ =962±60 mb for the same.We have found the relative neutron activation methodis more accurate than the absolute neutron activation method to stabilize the value ofneutron flux through the use of the monitor reaction.}, keywords_ku = {Neutron source,neutron activation,cross-section}, url = {https://jgu.garmian.edu.krd/article_67096.html}, eprint = {https://jgu.garmian.edu.krd/article_67096_9f8207f25a9b75fe81109e693aafa16d.pdf} }