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Quantitative analysis of piping configuration effects on the hydraulic performance of the CAP1400 reactor coolant pump's core components via source term and modal decomposition methods

Author

Listed:
  • Guo, Zhenyang
  • Xiang, Xiaxia
  • Lu, Yeming
  • Wang, Xiaofang
  • Wang, Weijun

Abstract

The CAP1400 passive pressurized water reactor unit stands as the largest third-generation nuclear power facility of its kind developed in China. To elucidate the influence of piping and key equipment within the nuclear island's primary loop system on the operational characteristics of the CAP1400 reactor coolant pump (RCP), this research established a three-dimensional numerical simulation approach for the nuclear island's primary loop, based on the source term methodology. By introducing source terms and porous media models to simplify the steam generator and reactor pressure vessel, the computational bottleneck associated with simulating large-scale nuclear island full loops was effectively mitigated, thereby achieving a compromise between computational efficiency and precision. The study contrasted the hydraulic performance, pressure fluctuation, hydraulic excitation forces, entropy production distribution, and SPOD modal information of key RCP components under two operational scenarios: independent operation (RCP-I) and operation within the piping configuration system (RCP-C). The findings indicate that: (1) The simulation of the nuclear island primary-side full loop has been successfully implemented employing the source term and porous medium approach, yielding high accuracy and aligning well with experimental data. (2) Compared to the independent operation condition, the RCP within the piping configuration system exhibits a slight head increase of 0.21 m; however, its efficiency declines markedly by 2.64%, accompanied by an escalation in internal energy loss. (3) Entropy production analysis reveals that the significant increase in energy loss predominantly originates from the vane region and the inlet region, with augmentations of 77.0% and 55.4%, respectively. (4) Further examination of the SPOD modes indicates that the piping configuration prematurely induces flow separation at the impeller leading edge and exacerbates backflow in the vane outlet region, which constitutes the primary cause of the pump's overall performance deterioration and the rise in internal energy loss. This research is anticipated to offer technical support for the simulation and assessment of large-scale nuclear islands.

Suggested Citation

  • Guo, Zhenyang & Xiang, Xiaxia & Lu, Yeming & Wang, Xiaofang & Wang, Weijun, 2026. "Quantitative analysis of piping configuration effects on the hydraulic performance of the CAP1400 reactor coolant pump's core components via source term and modal decomposition methods," Energy, Elsevier, vol. 347(C).
  • Handle: RePEc:eee:energy:v:347:y:2026:i:c:s0360544226002781
    DOI: 10.1016/j.energy.2026.140176
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    References listed on IDEAS

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    1. Ye, Jin & Li, Wei & Wang, Xingyuan & Ji, Leilei & Agarwal, Ramesh & Lu, Zhanxiong, 2025. "Reduced-order variational Mode decomposition of transient flow fields in mixed-flow pumps during startup," Energy, Elsevier, vol. 334(C).
    2. Kan, Kan & Zhang, Qingying & Xu, Zhe & Zheng, Yuan & Gao, Qiang & Shen, Lian, 2022. "Energy loss mechanism due to tip leakage flow of axial flow pump as turbine under various operating conditions," Energy, Elsevier, vol. 255(C).
    3. Guo, Zhenyang & Chen, Yanmu & Lu, Yeming & Wang, Tongjun & Wang, Xiaofang & Jiang, Xiaomo, 2024. "Application of the fast 3D simplified simulation method for the large CAP1400 nuclear island evaporator based on the coupled source term method," Energy, Elsevier, vol. 299(C).
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