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

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. (author)