Strojniški vestnik - Journal of Mechanical Engineering 62(2016)4, 231-242 © 2016 Journal of Mechanical Engineering. All rights reserved. D0l:10.5545/sv-jme.2015.3192 Original Scientific Paper Received for review: 2015-11-12 Received revised form: 2016-01-25 Accepted for publication: 2016-02-09 Flow Unsteadiness and Pressure Pulsations in a Nuclear Reactor Coolant Pump Dan Ni* - Minguan Yang - Bo Gao - Ning Zhang - Zhong Li Jiangsu University, School of Energy and Power Engineering, China Unsteady flow induced by rotor-stator interaction is detrimental to the safe operation of the nuclear reactor coolant pump, so it is essential to clarify flow structures and pressure pulsations in such pumps, especially within the spherical casing. In this paper, unsteady flow characteristics in a mixed-flow nuclear reactor coolant model pump were investigated using large-eddy simulation (LES) method. Results show that at the nominal flow rate, in two particular diffuser channels near the spherical casing discharge nozzle, the flow structures are uneven compared with that in the other flow channels. The reason is associated with the position of the flow channel with respect to the spherical casing nozzle. Large- scale flow separation and backflow structures easily occur at the regions near these two channels. In the right and the middle region of the casing nozzle, due to the large-scale separate flow and high vorticity magnitude, unsteady flow structures are more complicated in comparison with the other regions. It has been found that the vorticity spectra and the pressure spectra almost have the same main excitation frequencies. Therefore, it has been confirmed that for particular regions pressure pulsations are determined by the shedding vortex wake from the diffuser blade trailing edge of the nuclear reactor coolant model pump. Keywords: nuclear reactor coolant pump, flow unsteadiness, pressure pulsation, vorticity magnitude Highlights • Numerical investigation of flow unsteadiness and pressure pulsation in a nuclear reactor coolant pump. • Flow separations and backflows easily occur at the diffuser channels near the discharge nozzle region. • At the left region of the casing, the discharge nozzle is affected significantly by an intense rotor-stator interaction effect. • In the right and middle of the casing nozzle, unsteady flow structures are more complicated. • An unsteady vortex-shedding effect would motivate evident component in pressure spectrum. 0 INTRODUCTION A nuclear reactor coolant pump (RCP) [1], the device in the reactor core and the steam generator that transfers the heat energy [2], is the "heart" of a nuclear reactor driving the circulation flow of the coolant in the main loop [3]. The nuclear reactor coolant pump is the only rotating part of the nuclear island, so it belongs in a nuclear safety grade one facility. Moreover, it is also the main energy-consuming equipment in the nuclear power plants, which must be guaranteed to operate continuously over a long term and without trouble. An investigation on the internal flow in the mixed-flow nuclear reactor coolant pump is one of the key problems for the development of reactor coolant pumps in large pressurized water reactors. Some investigations have been conducted to study the design of the mixed-flow pump [4] and [5] and flows instabilities [6] and [7]. However, most of them only focus on the unsteady pressure pulsation in impeller [8] and [9] or the performance of the nuclear reactor coolant pump [10] and [11]. The unsteady flow structure of a mixed-flow nuclear reactor coolant pump, especially in certain specific regions, is very important to the safety analysis of a nuclear reactor, as it could generate serious flow-induced vibration, threatening the pump integrity [8]. Therefore, a comprehensive analysis and prediction of pressure pulsation caused by intense rotor-stator interaction are essential for the design of the mixed-flow nuclear reactor coolant pump [12] and [13]. At present, in order to improve the efficiency and stable operation of the nuclear reactor coolant pump, the complicated internal unsteady flow structures should be thoroughly illustrated. The nuclear reactor coolant pump has a special structure equipped with a spherical casing, which determines a typical and complex flow pattern within the pump. Knierim et al. [14] designed a new type of reactor coolant pump for a 1400 MW nuclear power plant. The impeller and diffuser were gradually optimized based on the computational fluid dynamics (CFD). The volute casing is a spherical shape with a discharge nozzle facing the impeller, and the flow structures in the region around the discharge nozzle are uniform. The region of the discharge nozzle itself is characterized by the fact that the flow below the outlet port is divided into two parts. One portion flows out of the casing discharge nozzle, whereas the other portion circulates around the casing once more prior to exiting. Kato et al. [15] and [16] described internal flows of a high-specific-speed mixed-flow pump at low flow rates using large-eddy simulation (LES), and it showed that the head-flow curve exhibited weak *Corr. Author's Address: Jiangsu University, School of Energy and Power Engineering, Zhenjiang 212013, China 231 Strajniski vestnik - Journal of Mechanical Engineering 62(2016)4, 231-242 instability characteristics. Posa et al. [17] reported the LES method used in a mixed-flow pump, where a structured cylindrical coordinate solver with optimal conservation properties was utilized in conjunction with an immersed-boundary method. Moreover, the overall agreement with the experimental results was excellent, demonstrating the robustness and feasibility of the approach in rotating machinery applications. It demonstrated that the LES method was adequate to predict complicated flow patterns of a high-specific-speed mixed-flow pump. With the development of non-contact measuring techniques, unsteady particle image velocimetry (PIV) [18] and laser Doppler velocimetry (LDV), measuring techniques are often applied to investigate complex unsteady internal flow in pumps, in such a way that no external disturbance is imposed on the flow field. Miyabe et al. [6] and [7] used PIV and pressure fluctuation measurements to investigate the propagation mechanism of a rotating stall in a mixed-flow pump. It was found that unstable performance was caused by periodic large-scale abrupt backflow generated from the diffuser to the impeller outlet. However, most research focuses on the design and the instability flow of the impeller and diffuser in a mixed-flow pump [19] to [22], and unsteady flows in a mixed-flow nuclear RCP with the specific spherical casing are rarely conducted. Consequently, true internal flow structures have not been thoroughly revealed. In this study, based on the LES method, the internal unsteady flow in a mixed-flow RCP model pump is studied. Monitoring points are mounted on the impeller inlet, diffuser channels, and spherical casing to achieve pressure pulsation characteristics. Finally, pressure pulsations and complicated flow structures are combined together to clarify flow unsteadiness in the RCP model pump. 1 NUMERICAL METHOD 1.1 Governing Equations By neglecting the incompressible effect of the fluid, LES governing equations [15] to [17] can be described in the following form. — (pu ) = 0, dx (1) di -d ( — ^ d da* I d* dT (2) —(p-i) +—(p--j) = —I n— l- — -—, (2) dt dx dx I dx ) dx dx j v j where ut (i = 1, 2, 3) is the grid-scale velocity component, p is the grid-scale static pressure, p is the density and ^ is the kinematic viscosity, and at] is the stress tensor having the form of Eq. (3). du. du- Ml — + — dx dx 2 dui -n— 3 dx ' (3) where öj is Kronecker delta. Tj is the sub-grid-scale (SGS) stress tensor, which is defined in Eq.(4). : pU^Uj (4) In this study, the Smagorinsky-Lilly SGS fixed-coefficient model [23] is applied to close the equations. In this model, the eddy viscosity is defined in Eq. (5). = PLS S ■ (5) where LS is the mixed length of the grid and |S| =