基于CFD仿真的核主泵流动特性研究

发布时间：2018-01-11 21:37

本文关键词：基于CFD仿真的核主泵流动特性研究　出处：《水泵技术》2016年05期 　论文类型：期刊论文

【摘要】：为研究核主泵水力部件的流动特性,基于N-S方程及k-ωSST湍流模型,对核主泵水力部件多个流量点进行三维流动数值计算,研究了核主泵内不同流量工况下的流动特征,并对额定工况下的性能数据与试验数据进行了对比。结果表明,基于CFD分析的方法可有效预测核主泵的水力性能,获取内部流动细节。在额定设计工况下,核主泵流态均匀稳定,水力性能优良。通过与非设计流量工况的对比,较全面地分析了该核主泵流动特性,为解决核主泵水力部件设计和优化提供了有益的参考。
[Abstract]:In order to study the flow characteristics of the hydraulic components of the nuclear main pump, three dimensional flow numerical calculation was carried out on the basis of N-S equation and k- 蠅 SST turbulence model. The flow characteristics of nuclear main pump under different flow conditions are studied, and the performance data under rated conditions are compared with experimental data. The method based on CFD analysis can effectively predict the hydraulic performance of the nuclear main pump and obtain the internal flow details. Under rated design conditions, the flow state of the nuclear main pump is uniform and stable. The flow characteristics of the nuclear main pump are analyzed comprehensively, which provides a useful reference for the design and optimization of the hydraulic components of the nuclear main pump.
【作者单位】：中核国电漳州能源有限公司;上海电气凯士比核电泵阀有限公司;
【分类号】：TM623;TH38
【正文快照】： 与|= 核反应堆冷却剂栗(简称核主泵)是确保核电站安全可靠运行最为关键的动力设备,属于核I级泵,其主要作用是实现反应堆冷却剂在一回路系统内的循环以供冷却堆芯,被喻为核电站的心脏叭核主泵的特点是运行流量大、功率高,并要求在高温高压强辐射的环境下长时间安全可靠高效运

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