Method for defining the concentration of fissile materials in radioactive waste

Abstract

In the work the development materials of an industrial technique definition of fission materials concentration in radioactive waste are resulted. The active analysis lays on the basis of a technique. Researched samples were irradiated with flows of neutrons received on the basis of the electron linear accelerator. Experiment was carried out on ELE - 300 NSC KIPT using neutron - making target made of Pb (5 cm in diameter and 4 cm in thickness). At an electron beam energy of 20 МeV and an average current of 1 mА such a target can produce a total neutron flux of about 2x10¹⁰s⁻¹. The achieved sensitivity by definition of concentration ²³⁵U is at the level 10⁶ g/g.