FIELD: measuring.
SUBSTANCE: invention relates to a method for estimating the total cross section of interaction of a material with thermal neutrons. In the neutron activation analysis installation, implemented on basis of 252Cf radionuclide neutron source in the activation zone, an indicator plate is placed in the neutron collimator in the corresponding position, a sample of the analysed material is placed in front of the indicator on the path of the neutron beam. Sample is irradiated with a neutron flux with intensity of 109 s-1 through 252Cf fission neutron moderator made of organic glass and providing a maximum thermal neutron flux in the activation zone for 9-12 hours. Measurement of the induced activity of the material and the europium-based indicator plate is carried out for 2-5 hours in γ-spectrometric complex based on a coaxial HPGe detector. Total cross-section of interaction of thermal neutrons with the material is determined from the change in the induced activity of the indicator plate.
EFFECT: possibility of increasing the rate of estimating the total cross section of interaction of materials with thermal neutrons while simplifying the design of the measuring apparatus.
2 cl, 1 tbl
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Authors
Dates
2024-08-26—Published
2024-05-03—Filed