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核反应堆水池流固耦合动力特性分析
Fluid-structure Coupling Dynamic Characteristic Analysis of Nuclear Reactor Pool
【Author】 AI Hong-lei,ZHANG Yi-xiong (National Key Lab.of Reactor System Design Technol.,Chengdu 640041,China)
【机构】 核反应堆系统设计技术国家级重点实验室;
【摘要】 考虑到三维流固耦合问题计算规模较大,为了对核反应堆水池内流体的晃动特性有一个比较完整的认识,采用基于势流的流固耦合单元可以大大地缩减流固耦合计算的规模,其对于实际工程中复杂核反应堆水池的三维动力特性分析以及进一步的动力响应分析具有重要的意义。实际的算例分析表明,采用基于势流的流固耦合单元求解核反应堆水池动力问题是十分有效的和可靠的。分析了流体的可压缩性对流体波动频率的影响,为下一步动力分析中对流体可压缩性的假设提供了参考依据。
【Abstract】 In order to understand the sloshing characteristic of the fluid in Nuclear reactor pool and its effect on the dynamic characteristic of the pool,a potential-based fluid formulation was implemented in the fluid-structure coupling dynamic analysis.The calculation scale was reduced to a great extent by using the formulation,which is very important for the dynamic characteristic analysis of some complicated pool in nuclear power plants.The validity and the reliability of the formulation were verified by a numerical example.The compressibility effect of the fluid in container on the sloshing characteristic was also analyzed,and the evidence for compressibility assume of fluid in the further analysis was gotten.
【Key words】 nuclear reactor pool; fluid-structure coupling; dynamic characteristic;
- 【会议录名称】 四川省力学学会2010年学术大会论文集
- 【会议名称】四川省力学学会2010年学术大会
- 【会议时间】2010-09-01
- 【会议地点】中国四川成都
- 【分类号】TL334
- 【主办单位】四川省力学学会(Sichuan Society in Mechanics)