STUDY OF NEUTRON YIELD FOR THE 241Am9Be SOURCE

Abstract

Beryllium chemical combination has a considerable effect on the design and fabrication of the241Am9Be neutron source. In this investigation the beryllium combinations were studied as a generator ofneutrons with various mass percentage, and the neutron yields were also calculated using the results of theALICE and SRIM codes calculations per unit incident charge. The neutron yields of Beryllium Hydride,Beryllium Carbide, Beryllium Hydroxide, Beryllium Oxide, Beryllium Acetate, Beryllium Acetylacetonateand Beryllium Sulfate were calculated as 4397.992107 , 1511.184107 , 976.609107 , 595.299 107 , 336.163107 , 169.62107 and 149.053107 respectively. Our calculations indicate that, the Beryllium Hydride is a proper material for use in the 241Am9Be neutron source.