摘要
针对海洋核动力平台在风浪流载荷联合作用下产生的动力响应带动平台上反应堆稳压器运动,引起其内部汽液介质晃动并造成反应堆压力额外波动及设备冲击等问题,采用Fluent软件建立了流体仿真模型,并基于流体体积(VOF)方法对稳压器内部液体的晃动进行数值模拟,得到了风浪流载荷不同工况下(包括极端情况)液体的晃动过程、稳压器壁面平均静压强和内部压力等参数的变化及波动范围;另外还对防晃液装置的防晃效果进行了仿真和分析,为稳压器进一步的防晃研究和安全设计提供研究基础和理论参考。
An ocean nuclear power platform will generate a dynamic response under the combined action of wind, wave and current loads, and this drives movement of the pressurizer on the platform, resulting in liquid sloshing inside the pressurizer. The liquid sloshing inside the pressurizer on an ocean nuclear power platform will cause additional pressure fluctuations and has a noticeable impact. This study used Fluent software to establish a fluid simulation model and carry out numerical simulations based on the volume of fluid(VOF) method. We obtained a description of the swaying process of a liquid under different loads, including extreme cases, as well as the average wall static pressure, and the fluctuation range of the internal pressure. In addition, the effect of an anti-sloshing device is simulated and analyzed. This work provides a basis and theoretical reference for further study of liquid sloshing and safe design of the pressurizer.
作者
曹知
陈平
郝天才
郭文星
CAO Zhi;CHEN Ping;HAO TianCai;GUO WenXing(College of Mechanical and Electrical Engineering,Beijing University of Chemical Technology,Beijing 100029;China Nuclear Power Research Institute Co.Ltd.,Shenzhen 518031,China)
出处
《北京化工大学学报（自然科学版）》
CAS
CSCD
北大核心
2019年第1期84-90,共7页
Journal of Beijing University of Chemical Technology(Natural Science Edition)
