Analysis and Optimization of Unsteady Flow in a Double-Suction Centrifugal Pump for a Cooling-Water Supply System in a N
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https://doi.org/10.1007/s11630-020-1252-z
Article ID: 1003-2169(2019)00-0000-00
Analysis and Optimization of Unsteady Flow in a Double-Suction Centrifugal Pump for a Cooling-Water Supply System in a Nuclear Reactor YAN Hao1, SU Xiaozhen1*, SHI Haixia1, CHENG Maosheng2, LI Yunqing1 1. School of mechanical engineering, Hefei University of Technology, Hefei 230009, China 2. Anhui Line Pump Co., Ltd, Ningguo 242300, China © Science Press, Institute of Engineering Thermophysics, CAS and Springer-Verlag GmbH Germany, part of Springer Nature 2020
Abstract: The management of a cooling-water supply system in a nuclear reactor is performed by valve and reactor coolant pump (RCP) control, which regulates both the pressure and the discharge between certain limits. However, the RCP has a significant unsteady flow when operating at different conditions. The unsteady pressure pulsation and radial force vector are difficult to calculate because these are affected by the transient properties of the unsteady flow. This study explores the use of a commercial Computational Fluid Dynamics (CFD) code to comprehensively estimate the unsteady flow of the RCP. The full 3D-URANS equations were solved for different flow rates, and some optimised cases for the unsteady flow were proposed. The results showed that the numerical predictions were validated with the experimental data of a model pump. The code was used to estimate the velocity streamlines, pressure pulsation and radial force vector in the steady and transient conditions. The flow rates were not equal for the inner and outer passage in the double volute casing. Additionally, the pulsation of the pressure and radial force was effectively reduced by optimising the staggered angle α. An optimal case was observed when α =30°.
Keywords: unsteady flow, reactor coolant pump (RCP), radial force, pressure pulsation
1. Introduction In a cooling-water supply system, a reactor coolant pump (RCP) of a nuclear power plant between the reactor and the steam generator functions much like the human heart and operates in a whole service life. The RCP, as a key component of a reactor auxiliary cooling system, collects heat from the reactor core and exchanges it via heat exchangers by using a coolant, as shown in Fig. 1. For the reactor auxiliary cooling systems, it is typically used as a double-suction centrifugal pump. The pumps are designed based on performance under uniform flow; however, this can lead to unsteady flow between the
Received: Mar 14, 2019
AE: DU Juan
stator (double volute casing) and rotator (impellers) [1,2]. The complex geometry might influence the hydraulic performance and stability of the pump. If the RCP ceases to work at any point, the heat generated from nuclear fission reactions is not exchanged via the circulating coolant, and the ensuing malfunction causes serious issues in the reactor’s operation within a matter of minutes. Therefore, an effective approach should be developed to mitigate the unsteady flow of the RCP. This article’s primary focus is to ensure the stabl
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