Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Diagnostics of the crisis state of the PWR reactor on the basis of model of steaming of channel

3/25/2019 2019 - #01 Thermal physics and thermal hydraulics

Kachur S.A.

DOI: https://doi.org/10.26583/npe.2019.1.04

UDC: 621.039.56

The offered mathematical model allows to promote safety of functioning of the such difficult system, as atomic reactor, defining a boiling process as one of above all displays of his functioning. A model enables in good time to forecast, localize and remove the emergency situation related to worsening of taking warm, due to the use of the direct measurings of parameters of heat exchange, minimization of indirect calculations and application of empiric formulas. The offered model extends the class of the decided tasks, I.e. it allows to pass from the task of authentication of parameters and state of nuclear reactor to the task of prognostication of crisis of heat exchange.

The offered way of providing of safe management allows to use all present hardwares of control and the reactor management and does not require additional material expenses for the reconstruction of the systems. Application of forecasting mathematical model enables to shorten time on the decision-making, expose the crisis of heat exchange on an early stage, which is not fixed by other control and control systems. It allows to prevent crisis situations without the use shield, application of which worsens the operating parameters of the reactor setting from appearance of transitional processes and poisoning of reactor by xenon.

The analysis of existent models and methods of diagnostics of nuclear reactor showed that their basic task consisted in authentication of current status of reactor on the basis of information by acting one from sensors, determination of possible limits of basic parameters, authentications of current situations. The functions of prognosis, as such, are absent.

It is possible to define the following ways of modification of the existent intrareactor control systems: 1) prognostication of intrareactor anomalies; 2) prognostication of the state of reactor and crisis situations; 3) transmission of functions of operator to the intellect systems.

Possibility of rapid diagnostics of the state of channel with the use of neuronet technologies is considered.

A model can be used for development of the systems of diagnostics of intrareactor anomalies and adaptive control systems by thermal power of nuclear reactor of the type PWR.

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nuclear reactor crisis of heat exchange energy-release thermalphysic model identification neural nets

Link for citing the article: Kachur S.A. Diagnostics of the crisis state of the PWR reactor on the basis of model of steaming of channel. Izvestiya vuzov. Yadernaya Energetika. 2019, no. 1, pp. 41-50; DOI: https://doi.org/10.26583/npe.2019.1.04 (in Russian).

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