300MWe级核电站主泵流固耦合传热研究  

Study on Fluid-Solid Coupling Heat Transfer in Reactor Coolant Pump of one 300MWe Nuclear Power Plant

作　　者：陈向阳[1] 袁丹青[1] 杨敏官[1] 袁寿其[1] 

机构地区：[1]江苏大学,江苏镇江212013

出　　处：《流体机械》2010年第1期19-22,4,共5页Fluid Machinery

摘　　要：反应堆冷却剂泵的流动、传热问题涉及计算流体力学和固体传热有限元学,流、固传热系统在交界面处边界条件的确定是一个重点。利用分区求解、边界耦合的方法将流体和固体作为一个整体研究,在交界面上先假定一个初始温度,再进行迭代计算。通过对计算结果进行分析,从而得到主泵实体及流体的温度分布与流体流动状态有密切关系,叶片温度受流动状态影响较大,轮毂处相对较小,叶轮叶片表面高温区类似涡状。为研究主泵流场、温度场和应力场的三场耦合问题,提供了依据。The problem of flow and heat in reactor coolant pump involves computational fluid dynamics and solid heat transfer. It is a key point to confirm the boundary condition for the fluid-solid coupling heat transfer system. The method of solving in every individual domain and coupling in interface which regards the fluid and solid problem as a whole was used in this paper. The as- sumed initiative temperature in interface is necessary before iteration. Through the analysis＇on results ,it is conclued that the distributions of temperature in the body and flow field of reactor coolant pump are related to flow condition and the biggest influence exists in blades but the other way round in hub. And the temperature distribution in surface of impeller blades is similar to eddy shape. This paper is the basis of three coupling field problem about flow, temperature and stress for reactor coolant pump.

关 键 词：反应堆冷却剂泵 流固耦合传热 边界耦合 三场耦合 

分 类 号：TH312[机械工程—机械制造及自动化]