Determination of the ²³⁸U concentration in concrete samples by registration of fission neutrons

In the work was to carry out and to improve the fission elements content tests of techniques for the concrete samples analysis of weight up to 0.5 kgs. The basis of this technique is the active analysis. Researched samples were irradiated with flows of neutrons received on the basis of the electron linear accelerator. The neutrons induce fissions in the samples. Experiment was carried out at ELE - 300 NSC KIPT. The technique allowing expressly, with a sufficient degree of reliability is checked up in operation to define the contents ²³⁸U in concrete samples. Achieved in the given experiment sensitivity makes ~ 10 g of uranium in a sample

Method for defining the concentration of fissile materials in radioactive waste

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