Neutron flux micro-distribution and self-shielding measurement in the Syrian Miniature Neutron Source Reactor

被引：0
|
作者：
Khamis, I [1 ]
Al-Somel, N [1 ]
Sarheel, A [1 ]
机构：
[1] Atom Enerty Commiss, Dept Phys, Damascus, Syria
来源：
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2004年 / 260卷 / 02期
关键词：
D O I：
10.1023/B:JRNC.0000027117.38511.4f
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
Measurement of neutron flux micro distribution within absorbing samples have been made using Dy and Au foils activated in cadmium filter for both thermal and epithermal regions, respectively. Self-shielding effect for highly absorbing material has been investigated for the purpose of activation analysis in the Syrian Miniature Neutron Source Reactor (MNSR). Self-shielding factors for both thermal and resonance regions have been evaluated. Measured and theoretical values of self-shielding factors have been compared. Correction expression of the neutron activation analysis measurement for self-shielding has been proposed.
引用
收藏
页码：413 / 416
页数：4
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