反应堆吊篮在泵致脉动压力载荷下的响应研究

反应堆结构的流致振动问题一直受到核工程界的广泛关注。主泵的泵致脉动压力是一个重要激励源，其将导致反应堆吊篮等部件周期性振动，长期运行会导致结构的疲劳损坏。为研究新设计的“华龙一号”反应堆吊篮在泵致脉动压力作用下的振动响应，本文首先分析反应堆吊篮所受的泵致脉动压力，而后建立吊篮有限元模型，对其在泵致脉动压力载荷下的动力学响应进行研究，并综合考虑湍流激励，评价吊篮在堆内构件流体作用下的整体影响。应力分析表明，吊篮各位置流致振动的最大应力强度小于疲劳应力限值，结构是安全的。但对于新设计的反应堆，或反应堆冷却剂系统更换新的主泵，则反应堆吊篮及堆内构件的泵致振动需受到重视。

Response of Reactor Core Barrel under Pump-induced Pressure Pulsation

The flow induced vibration (FIV) problems affect the safe operation of reactor. It is paid attention to by the nuclear engineering for a long time. The pump-induced pressure pulsation is an important excitation source of FIV, which will lead to periodic vibration of reactor core barrel (CB) and other components. It may cause resonance and have the adverse impact on the fatigue life of structure. In order to study the vibration of core barrel (CB) of newly designed Hualong No.1 reactor under pump-induced pressure pulsation, the finite element model of the CB was established and the dynamic response characteristics under pump-induced pressure pulsation were analyzed. Considering the turbulence excitation, the overall response of the CB under the FIV was evaluated. The stress analysis shows that the maximum flow induced stress intensity at each position of the CB is less than the fatigue stress limit, and the structure is safe. However, for the newly designed reactor or the change of the main pump in the reactor coolant system, the pump induced vibration of the reactor system should be paid attention to.