A.V. Ianushevich, V.D. Sevastianov
FSUE “VNIIFTRI”, Mendeleevo, Moscow region
sevast@vniiftri.ru
Al’manac of Modern Metrology № 1 (21) 2020, pages 148–162
The possibility of application of the open fission source of 252Cf to accurately determine the flux of radionuclide neutron sources is considered.
A method for measuring the flux consists in determining its fission-fragment activity and multiplying it by the average value of the number of neutrons emitted by one act of spontaneous fission of the 252Cf nuclide.
Methods for the accurate measurement of the fragmentation activity of the 252Cf nuclide are considered and put into practice.
Key words: fission constant, radionuclide sources of neutrons, fission of a nuclide, fragmentation activity.
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