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KAKAVAND, T., HAJI-SHAFEIEHA, M., GHAFOURIAN, H.. (1388). STUDY OF NEUTRON YIELD FOR THE 241Am9Be SOURCE. , 33(3), 277-280. doi: 10.22099/ijsts.2009.2224
T. KAKAVAND; M. HAJI-SHAFEIEHA; H. GHAFOURIAN. "STUDY OF NEUTRON YIELD FOR THE 241Am9Be SOURCE". , 33, 3, 1388, 277-280. doi: 10.22099/ijsts.2009.2224
KAKAVAND, T., HAJI-SHAFEIEHA, M., GHAFOURIAN, H.. (1388). 'STUDY OF NEUTRON YIELD FOR THE 241Am9Be SOURCE', , 33(3), pp. 277-280. doi: 10.22099/ijsts.2009.2224
KAKAVAND, T., HAJI-SHAFEIEHA, M., GHAFOURIAN, H.. STUDY OF NEUTRON YIELD FOR THE 241Am9Be SOURCE. , 1388; 33(3): 277-280. doi: 10.22099/ijsts.2009.2224

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

Iranian Journal of Science
مقاله 8، دوره 33، شماره 3، آذر 2009، صفحه 277-280    اصل مقاله (38.07 K)
نوع مقاله: Research Note
شناسه دیجیتال (DOI): 10.22099/ijsts.2009.2224
نویسندگان
T. KAKAVAND1؛ M. HAJI-SHAFEIEHA* 2؛ H. GHAFOURIAN3
1Physics Department, Zanjan University, Zanjan, I. R. of Iran
2Islamic Azad university of Qazvin, Qazvin, I. R. of Iran
3Atomic Energy Organization of Iran, Tehran, I. R. of Iran
چکیده
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.
کلیدواژه‌ها
Neutron؛ Beryllium؛ Americium؛ ALICE Code؛ SRIM Code؛ Neutron Yield
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