Персона: Денисенко, Анастасия Павловна
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Методы восстановления характеристик нейтронных спектров по показаниям спектрометров с ограниченным числом каналов
2021, Денисенко, А. П., Денисенко, Анастасия Павловна, Рябева Елена Васильевна
Experimental determination of the induced activity in activation detectors of a complex geometric shape
2020, Ibragimov, R. F., Kokorev, Y. A., Denisenko, A. P., Ryabeva, E. V., Samosadny, V. T., Hasnaoui, H., Ибрагимов, Ренат Фаридович, Кокорев, Яков Александрович, Денисенко, Анастасия Павловна, Рябева, Елена Васильевна
Methods for Estimating a Neutron Spectrum Using a Diamond Detector, Plastic Scintillator, and Set of Activation Detectors
2023, Ryabeva, E. V., Denisenko, A. P., Ibragimov, R. F., Urupa, I. V., Рябева, Елена Васильевна, Денисенко, Анастасия Павловна, Ибрагимов, Ренат Фаридович, Урупа, Илья Викторович
Experimental determination of the induced activity in activation detectors of a complex geometric shape
2020, Ibragimov, R. F., Kokorev, Ya. A., Denisenko, A. P., Ryabeva, E. V., Samosadny, V. T., Hasnaoui, H., Ибрагимов, Ренат Фаридович, Кокорев, Яков Александрович, Денисенко, Анастасия Павловна, Рябева, Елена Васильевна
© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The paper presents the results of experimental determination of the induced activity in copper"/aluminum"based activation detectors when irradiated with neutrons with energy of about 14 MeV. The activation detectors were square"shaped metal plates with a thickness from 1.0 to 1.5 mm and a side size about 5.0 cm. Such samples require a specific method for measuring the induced activity, which will take into account large sizes of the plate relate to the size of gamma"detector or neutron source. The detectors described in this work can be used to study low"intensity neutron fluxes (with a flux density of up to 106n/cm2·s). It is shown that, when working with such detectors, the usual methods for calculating the induced activity in thin activation detectors are applicable, with corrections that take into account the emerging features of the "neutron source - activation detector" and "activation detector - secondary radiation detector" geometries. The effects of absorption of primary and secondary radiation by the detector substance are also revealed. The Geant4 tools were used to calculate the geometric factors and theoretical induced activity value. The study confirms the applicability of such activation detectors for solving the problem of determining the yield of neutrons with energy of about 14 MeV from a neutron generator target. The results of the experiments coincide, within the margin of error, with the results of simulations performed using the Geant4 tools.
Characteristics of ZnS(Ag) + 6LiF Scintillator-Based Detector Used as a Neutron Dosimeter
2023, Kolesnikov, S. V., Denisenko, A. P., Ryabeva, E. V., Колесников, Святослав Владимирович, Денисенко, Анастасия Павловна, Рябева, Елена Васильевна