Corresponding author: Tatyana A. Bokova ( tatabo@bk.ru ) Academic editor: Boris Balakin
© 2020 Aleksandr V. Beznosov, Pavel A. Bokov, Aleksandr V. Lvov, Tatyana A. Bokova, Nikita S. Volkov, Aleksandr R. Marov.
This is an open access article distributed under the terms of the Creative Commons Attribution License (CC BY 4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.
Citation:
Beznosov AV, Bokov PA, Lvov AV, Bokova TA, Volkov NS, Marov AR (2020) Experimental studies into the performance of the lead coolant axial pump wet ends to justify main circulation pumps for the HMLC reactor plant circuits. Nuclear Energy and Technology 6(3): 143-147. https://doi.org/10.3897/nucet.6.57736
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The paper presents the results of the studies to justify the design solutions for the main circulation pumps of the heavy liquid-metal cooled reactor plant circuits. A substantial difference has been shown in the performance of pumps for the heavy liquid-metal coolant transfer. The studies have confirmed the qualitative difference in the cavitation performance of coolants, the state of the gases and vapors they contain, the influence of supply and discharge devices, and the effects of the impeller blade section performance and geometry and the hub-tip ratio on the pump performance. The studies were performed based on NNSTU’s lead-cooled test facilities with the coolant temperature in a range of 440 to 550 °C and the coolant flow rate of up to 2000 t/h. The outer diameter of the impellers and the straightening devices was about 200 mm, and the thickness of the flat 08Kh18N10T-steel blades was 4.0 mm and that of the airfoil blades was up to 6.0 mm. The pump shaft speed changed in a stepped manner from 600 rpm to 1100 rpm after each 100 rpm.
The studies were conducted to justify the engineering and design solutions for pumps as applied to conditions of small and medium plants with fast neutron lead cooled reactors currently under investigation at NNSTU (BRS-GPG). The experimental results can be recommended for use to design other HLMC transfer pumps.
Fast neutron reactor, main circulation pump, heavy liquid-metal coolant, impellers, impeller blades, pump supply and discharge
There is no currently experience of designing and operating pumps to transfer heavy liquid-metal coolant (Pb, Pb-Bi eutectics) (HLMC) as applied to reactor plants (
Cavitation behavior of HLMC in the considered conditions was explored and determined at the initial stage. The absence of conventional vaporous cavitation in the reactor circuit conditions was experimentally confirmed using independent methods. The conditions for its occurrence, development, and progression have been determined (
The experimental studies were performed as applied to the conditions of small plants with fast neutron lead and lead-bismuth cooled reactors with horizontal steam generators (BRS-GPG) under investigation at NNSTU (
Except as otherwise specified (with beryllium and aluminum based coating formation), protective coatings were formed on the surfaces of the pump wet end structural materials and maintained by oxygen control in the test bench lead coolant thanks to which the concentration of the thermodynamically active oxygen in lead was kept in a range of 10–5 to 100.
The initial stage in the exploratory test series consisted in determining experimentally the dependences of the test bench axial pump performance (head, delivery rate, efficiency) on the scalable wet end structural components, the composition and geometry of which were specified in the test procedure program.
The following experiments were conducted at stage 1.
The next investigation stage involved a comparative analysis of the obtained results. The wet end components were chosen based on the analysis results, with which the pumps had the maximum performance (head, delivery rate, efficiency), and manufactured with such flat-blade impeller parameters. The results of testing the optimized pump wet end design have shown the following.
As shown by the results of the test’s stage 1 (
a) the flat-blade designs with the flat blade incidence of α = 20°, the blade inlet bending angle of 4°, and the outlet bending angle of 0° (curve 2);
b) the flat-blade design with the flat blade incidence of α = 20°, the inlet bending angle of 0°, and the outlet bending angle of 8° (curve 3);
c) the best blade system design of those tested earlier, with aluminum-based protective coatings and airfoil blades (curve 4).
The pump delivery rate in the event of the optimized design was 10 to 15% excessive (Fig.
The obtained experimental data takes into account the specific nature of the HLMC effects on the pump wet end components and are recommended for use when justifying the reactor coolant pump designs for heavy liquid-metal cooled reactor plants.