Персона: Федоров, Владимир Алексеевич
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Testing device for neutron flux monitoring equipment
2020, Alyaev, I. V., Fedorov, V. A., Selyaev, N. A., Parishkin, Y. A., Федоров, Владимир Алексеевич, Селяев, Николай Анатольевич, Парышкин, Юрий Алексеевич
© 2020 Elsevier B.V.This report describes a testing device capable of emulating neutron fission chamber signals over their whole operating range. The device assists in the design and testing of neutron flux monitoring equipment including reactimeters, spectrometers, period meters and protection channels. Because of its hardware architecture, testing of neutron flux monitoring equipment can be done both in a laboratory environment and in-situ. Main characteristics of the device allow one to test the equipment over a wide range of count rates. A flexible mathematical algorithm, that is used to calculate the signal model of fission chambers, gives the opportunity for user to set the pulse shape and the charge spectrum such as those in a real fission chamber. It is also possible to set dynamic signals, for example, such as an exponentially varying count rate or a neutron point reactor kinetics signal with a configurable number of delayed neutron groups and constants. The device was verified by testing of the International Thermonuclear Experimental Reactor (ITER) neutron flux divertor monitor data acquisition system.
Study of the Data Acquisition System for ITER Divertor Neutron Flux Monitor Diagnostic
2020, Kashchuk, Y. A., Vorobiev, V. A., Fedorov, V. A., Martazov, E. S., Parishkin, Y. A., Selyaev, N. A., Федоров, Владимир Алексеевич, Мартазов, Евгений Сергеевич, Парышкин, Юрий Алексеевич, Селяев, Николай Анатольевич
© 1963-2012 IEEE.Diagnostic 'Divertor Neutron Flux Monitor (DNFM)' is one of the diagnostics to determine the neutron yield and the thermonuclear power of the ITER facility. To detect neutrons, this diagnostic uses three detector modules. The expected neutron flux in the detector module location is 106-1013 n cm-2 s-1. The neutron flux and the neutron yield should be measured with 1-ms time resolution and 10% maximum relative error. The detector module consisting of six fission chambers (FCs) is used to meet these requirements, and each FC signal is processed by pulse counting, Campbell, and current measurement methods simultaneously. According to the data of each measurement method, the normalized count rates (NCRs) of the FCs and the detector module and the neutron flux at its location are calculated. The data acquisition (DAQ) system processes the signals of the single detector module and transmits the data of the NCR and the neutron flux of each detector and entire detector module to the upper-level system. To verify the technique solutions, the DAQ system prototype was manufactured. To study the characteristics of this prototype, a set of laboratory tests was carried out. This article illustrates the structure of the DAQ system and the implementation of the FC signal processing methods. The results of the study of the DAQ system prototype for a single detector module are given.