Title of article :
STUDY OF NEUTRON YIELD FOR THE 241Am9Be SOURCE
Author/Authors :
KAKAVAND، T نويسنده Physics Department, Zanjan University, Zanjan, I. R. of Iran KAKAVAND, T , HAJI-SHAFEIEHA، M نويسنده Islamic Azad university of Qazvin, Qazvin, I. R. of Iran HAJI-SHAFEIEHA, M , GHAFOURIAN، H نويسنده Atomic Energy Organization of Iran, Tehran, I. R. of Iran GHAFOURIAN, H
Issue Information :
دوفصلنامه با شماره پیاپی 0 سال 2009
Abstract :
Beryllium chemical combination has a considerable effect on the design and fabrication of the
241Am?9Be neutron source. In this investigation the beryllium combinations were studied as a generator of
neutrons with various mass percentage, and the neutron yields were also calculated using the results of the
ALICE and SRIM codes calculations per unit incident charge. The neutron yields of Beryllium Hydride,
Beryllium Carbide, Beryllium Hydroxide, Beryllium Oxide, Beryllium Acetate, Beryllium Acetylacetonate
and 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.
Journal title :
Iranian Journal of Science and Technology Transaction A: Science
Journal title :
Iranian Journal of Science and Technology Transaction A: Science
