摘要
应用流-固耦合理论推导相似准则和模型设计。在反应堆1:10模型上进行了吊篮结构的空气和静水中模态分析试验,获得动态特性。在反应堆1:5水力回路上进行吊篮水力振动试验,测得了流体对吊篮表面脉动压力、加速度、应变等信号与流量关系。经信号处理后获得了流体载荷谱及各种响应参数。在这两个试验基础上对流-固耦合与流致振动定量分析,导出吊篮水流振动理论计算方程。计算了秦山核电厂300MW的吊篮水流振动的响应与试验相符合。试验分析结果表明吊篮水流振动在寿期内是安全的。
This paper describes the deduction of the resemblance criterion and the design of the test model by applying flow-solid coupling theory. The model analyses of a core barrel both in the air and stationary water were performed in a 1:10 model, thus obtaining the dynamic characteristic. In a 1:5 reactor model with a hydraulic closed loop, the inner structure and support were modeled for performing hydraulic vibration test of the core barrel. The flow induced pulse pressure of the core barrel and corresponding response were obtained by using miniature pressure capsule, strain gauge and accelerometer. Power spectrum, correlation functions, transfer function and amplitudes under different flow velocities were calculated. The hydraulic vibration test shows that the core barrel will be in safety during its 30-year life time.
出处
《核科学与工程》
CSCD
北大核心
1989年第1期8-19,5,共12页
Nuclear Science and Engineering
