秦山核电二期工程1#反应堆堆内构件流致振动现场实测

Site Measurement of Flow-induced Vibration of Reactor Internal of Unit 1 of Qinshan Phase II NPP Project

秦山核电二期工程反应堆堆内构件是以大亚湾核电站为有效原型堆的非原型II类,有必要在热态功能试验(HFT)期间进行堆内构件流致振动的有限实测,中国核动力院在国内首次完成了现场实测,获得了实堆吊篮和导向筒结构在冷却剂流动冲刷下的加速度和应变响应,并将实测结果与理论计算值、1:5模型试验结果进行了比较。结果表明,实测结果与理论计算值、1:5模型试验结果符合得较好。

Qinshan Phase Ⅱ NPP Project internals were classified as Non-Prototype Category Ⅱ, based on the Valid Prototype Daya Bay. It is necessary to carry out Flow Induced Vibration (FIV) limited measurements during Hot Functional Testing. This paper introduced the test purpose, installation of instrument, test case, test data analysis and process. Acceleration and strain response of the core barrel and strain response of CRGT were obtained. The test results were compared with predictive analysis results and results of 1:5 model test, and the consistence is good. The result in the field provided important data for safety evaluation of Qinshan Phase Ⅱ NPP Project, and provided benchmark for vibration surveillance and diagnostics of reactor operation.