Abstract:BeO is one of the most common moderator material for neutron moderation; due to its high density, neutron capture cross section and physicalchemical properties that provides usage at elevated temperatures. As it's known, for various applications in the field of reactor design and neutron capture, reaction cross-section data are required. The cross-sections of (n,α), (n,2n), (n,t), (n,EL) and (n,TOT) reactions for 9 Be and 16 O nuclei have been calculated by using TALYS 1.6 Two Component Exciton model and EMPIR… Show more
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