Estimation of the possibilities of a neutron generator-based source of thermalized neutrons for activation analysis

Characteristics of a source of thermal neutrons based on an evacuated NG-400 neutron generator with the maximum flux (Φ f ) 2 × 10 11 neutron/s for 14 MeV neutrons and 2 × 10 9 neutrons/s for 3 meV neutrons have been investigated. The possibilities of its application for neutron activation analysis have been estimated. The distribution, composition, and density (φ T ) values of the thermal neutron flux have been measured in the inner cavity of the moderator using activation detectors. φ T was 2 × 10 8 and 2 × 10 6 neutrons/cm 2 s for thermalized neutrons with energies of 14 and 3 MeV, respectively. The possibilities of the apparatus have been estimated theoretically and experimentally for the cases of thermalized neutrons of 14 MeV and 3 MeV.