程效锐,滕飞,张舒研,涂艺萱
Cheng Xiaorui,Teng Fei,Zhang Shuyan,Tu Yixuan

• 1:兰州理工大学能源与动力工程学院
• 2:甘肃省流体机械及系统重点实验室

摘要(Abstract)：

为了研究环形压水室结构对于核主泵水力性能的影响,在保证其他过流部件几何参数不变的前提条件下,以某型核主泵模型为研究对象,设计3种不同截面面积环形压水室的核主泵模型,并基于RNG k-ε湍流模型和滑移网格模型,对以上3种缩比模型内部流动进行全三维数值模拟,通过试验证实了数值计算数据与试验数据的吻合性与该数值模拟方法的可靠性。结果表明:在设计工况下运行,压水室截面面积变化对核主泵性能影响不大;偏离设计工况,适当增大压水室截面面积能够提高核主泵的扬程、效率和静压能占比,并改善压水室内部流动特征;而偏小的压水室截面面积会使其内部流动损失增大。在实际泵产品的设计和研究过程中,结构尺寸允许的条件下适当增大压水室截面面积有利于提高核主泵的整体性能。
In order to study the influence of the sectional area of the annular casing on the hydraulic performance of nuclear reactor coolant pump,under the condition that the geometric parameters of the rest flow passage components remain unchanged and with a certain type of nuclear reactor coolant pump model as the research object,three nuclear reactor coolant pumps with annular casings of different sectional area were designed. Based on the RNG k-ε turbulence model and the slip grid model,the full threedimensional numerical simulations of the internal flow of these three nuclear reactor coolant pump models were carried out. It was proved by experiments that the numerical calculation data were consistent with the experimental data and this numerical simulation method was reliable. The results show that the change of the sectional area of annular casing has little effect on the performance of the nuclear reactor coolant pump under the design conditions. Once the operation of the pump deviates from the design conditions,by appropriately increasing the sectional area of the annular casing,the head,efficiency and static pressure energy ratio of the nuclear reactor coolant pump can be improved,and the internal flow characteristics of the annular casing can be improved.However,the smaller sectional area of the annular casing will increase its internal flow loss. In the design and research process of the actual pump product,appropriate increase of the sectional area of the annular casing under the conditions allowed by structural dimensions is beneficial to improvement of the overall performance of the nuclear reactor coolant pump.

关键词(KeyWords)： 核主泵;压水室;截面面积;水力性能;数值模拟
nuclear reactor coolant pump;annular casing;sectional area;hydraulic performance;numerical simulation

Abstract:

Keywords:

基金项目(Foundation):

作者(Author): 程效锐,滕飞,张舒研,涂艺萱
Cheng Xiaorui,Teng Fei,Zhang Shuyan,Tu Yixuan

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