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Instruments and Systems: Monitoring, Control, and Diagnostics

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Development of Methods, Algorithms and Software for Monitoring Coolant Flow in the RBMK Nuclear Reactor
A.M. ZAGREBAYEV, E.O. POPOV

Methods, algorithms and software for monitoring the coolant flow in the fuel channel of the RBMK reactor are considered. The methods of determining the flow rate by methods independent of the standard one are given: according to the results of activation of the coolant and thermal hydraulic calculation. The possibilities of using the developed techniques and algorithms for diagnosing the operability of flowmeters are shown. The created software and the results of its use at one of the power units of the Kursk NPP are described.
Keywords: nuclear reactor, flow meter, coolant, diagnostics, thermohydraulic calculation, activation.


DOI: 10.25791/pribor.6.2023.1420

Pp. 73-77.

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