摘要
以国产百万千瓦级压水堆核电厂(CNP1000)的反应堆整体水力实验模型为对象,以实验工况为边界条件,开展堆芯下腔室导流围筒对流场影响的数值计算研究。使用计算流体力学(CFD)方法,通过堆芯流场验证计算和下腔室导流围筒多种孔径的流场计算分析,获得详细的堆芯内部流场流速与压力的分布情况,确定下腔室导流围筒对燃料组件入口流量分配、堆芯入口压力分布以及堆芯下腔室交混特性的影响,为堆芯内部结构的优化设计提供依据。
A numerical simulation is carded out to investigate the influence of shroud in lower plenum on flow field. The geometrical model and boundary conditions in the simulation are the same as the integral hydraulic experiment which based on domestic CNP1000 nuclear power plant. CFD method is adopted, the detailed velocity and pressure distributions in core under different shroud diameters have been obtained by numerical analysis and validation between experimental and computational results. Finally the influence of shroud on mass flow and pressure distributions in core inlet and the mixing characteristics in lower plenum have been confirmed, which could be used for the optimization of core construction.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2015年第1期148-151,共4页
Nuclear Power Engineering
关键词
数值模拟
导流围筒
流场
Numerical simulation, Shroud, Flow field
