Izvestiya vuzov. Yadernaya Energetika

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

Experimental research and testing of pump characteristics with nuclear reactor’s lead coolant

12/25/2015 2015 - #04 Chemistry, physics and technology of reactor coolants

Beznosov A.V. Lvov A.V. Bokov P.A. Bokova T.A. Shikhov D.V.

DOI: https://doi.org/10.26583/npe.2015.4.13

UDC: 621.039

The main circulation pump in the fast neutron reactors operating in specific conditions of the physical parameters of lead and lead-bismuth coolant. Scope last are qualitatively different from those of the thermodynamic characteristics of conventional heat transfer fluids: water and sodium. HLMC cavitation characteristics significantly different from those of other coolants of nuclear reactors.

Used in calculation methods pumps empirical and semiempirical dependences obtained in tests on the water, do not apply these techniques for the calculation and optimal design of pumps, pumping HLMC.

Test models MCP reactor BREST-OD-300 on the stand FT-4 NSTU showed that under the operating conditions of the experiment, inherent to reactor plants with HLMC, recorded a significant difference of actual flow and pressure of the pump and the expected settlement value in the design of the pump in the traditional techniques.

To justify the optimal design of the axial flow pump, pumping fluid into a high-temperature lead NSTU has developed a program of scientific research, the results of the individual steps that are presented in this article.

References

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heavy liquid metal coolant heavy liquid metal coolant reactor installation on fast neutrons MCP pump impeller cavitation pump head design centrifugal and axial vane-pump system