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Description
Thermal and epithermal neutron self-shielding correction factors for the (n,g) reaction in the 186W target were determined by simulation using the PHITS code. The 186W cylindrical target was in the form of metal powder diluted in an aluminum (Al) matrix at various concentrations. A Maxwellian neutron source with an average peak energy at 0.0253 eV was applied to the thermal neutron group and a 1/E distribution was applied to the epithermal neutron group. Neutron correction factors were investigated for different dilution concentrations of 186W in the 186W(Al) sample under two irradiation conditions: an isotropic neutron field and a collimated neutron beam. Additionally, neutron correction factors were calculated for various wire diameters under irradiation with a collimated neutron beam.
