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Activation method was applied to determine the thermal and epithermal neutron fluxes delivered by ²⁴¹Am-⁹Be &²³⁹Pu-⁹Be neutron double-source. Indium and gold metallic foils, as well as Sm₂O₃ and MnO₂ powders were exposed to this neutron source. In the irradiated samples^116mIn,¹⁹⁸Au, ⁵⁶Mn and ¹⁵³Sm radioisotopes were activated to saturation. The data obtained from the analysis of gamma spectra recorded from the neutron activated radioisotopes were used to calculate the thermal and epithermal neutron emitted by²⁴¹Am-⁹Be&²³⁹Pu-⁹Be double-source.

Keywords: neutron flux; neutron activation; gamma-ray spectrometry.