采用径向通风系统和径向-轴向-径向复合通风系统的大型核动力涡轮发电机流体-热场耦合对比研究

Machines Pub Date : 2024-05-10 DOI:10.3390/machines12050326
Shukuan Zhang, Fachen Wang, Yusen Zhang, Weijie Gao, Chuan Xiang
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引用次数: 0

摘要

随着能源需求的持续增长,核能的高能量密度、低排放、清洁等优势逐渐凸显。然而,随着核电站涡轮发电机容量的不断增大,损耗也随之增大,出现了严重的发热问题。设计有效的冷却系统对于提高转子的散热能力具有重要作用,尤其是在转子空间有限的情况下。本研究比较和分析了 1555 MVA 氢冷核电涡轮发电机转子采用径向直型冷却结构和径向-轴向-径向复合冷却结构的冷却效果。建立了两种冷却结构转子的三维流体热耦合模型,并提供了相应的边界条件。模型采用有限体积法求解。详细研究了转子内冷却氢气的流动规律和转子各部分的温度分布。与径向直线型冷却结构相比,采用径向-轴向-径向复合冷却结构可使转子磁场绕组的平均温度降低 4.5 °C。研究成果为大容量核电汽轮发电机转子冷却系统的设计和优化提供了参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A Comparative Study on Coupled Fluid–Thermal Field of a Large Nuclear Turbine Generator with Radial and Composited Radial–Axial–Radial Ventilation Systems
With the continuous growth of energy demand, the advantages of nuclear power, such as high energy density, low emissions, and cleanliness, are gradually highlighted. However, the increasing capacity of the turbine generator in nuclear power plants has led to greater losses and critical heating issues. Designing an effective cooling system plays an important role in improving the rotor’s heat dissipation ability, especially under the condition of limited rotor space. In this study, the cooling effects of the rotor using a radial straight-type cooling structure and a composited radial–axial–radial cooling structure are compared and analyzed for a 1555 MVA hydrogen-cooled nuclear turbine generator. Three-dimensional fluid thermal coupled models of the rotor with both cooling structures are established, and corresponding boundary conditions are provided. The models are solved using the finite volume method. The flow law of cooling hydrogen gas inside the rotor and the temperature distribution of various parts of the rotor are studied in detail. Compared with the radial straight-type cooling structure, adopting the composited radial–axial–radial cooling structure can reduce the average temperature of the rotor field windings by 4.5 °C. The research results provide a reference for the design and optimization of the rotor cooling system for large-capacity nuclear turbine generators.
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