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

Document Type : Research Note

Authors

1 Physics Department, Zanjan University, Zanjan, I. R. of Iran

2 Islamic Azad university of Qazvin, Qazvin, I. R. of Iran

3 Atomic Energy Organization of Iran, Tehran, I. R. of Iran

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.

Keywords

Iranian Journal of Science
Volume 33, Issue 3 - Serial Number 3
September and October 2009
Pages 277-280

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