广义非能动核级笼式调节阀抗震研究

Anti-Earthquake Research of Generalized Non-Energy Nuclear-Class Cage-Style Control Valve

抗震性能是衡量核电设备安全可靠性的重要指标之一,广义非能动核级笼式调节阀作为堆腔注水系统实现其流量调节功能的重要设备,对堆芯熔毁时的熔融物堆内滞留有着重要作用,必须对其进行抗震研究。利用限元分析方法进行模态分析,确定了调节阀的固有频率大于33 Hz,因此采用等效静力法进行抗震分析。根据计算结果确定危险部位进行应力评定,结果满足ASME核电规范与标准的相关要求。最后进行抗震实验和震后功能检测实验,抗震实验结果总体与仿真结果相符,震后功能检测实验表明调节阀未遭到破坏,且仍可以按照预期实现其调节功能。仿真和实验的结果均表明广义非能动核级笼式调节阀可以维持在地震条件下的结构完整性和功能稳定性。

Anti-earthquake performance is one of the important indicators for assessing the safety and reliability of nuclear power equipment.As an important equipment to achieve flow regulation in the reactor cavity injection system,the general non-powered nuclear-grade cage-type control valve plays a critical role in the retention of molten materials in the core during a meltdown scenario.Therefore,it is necessary to conduct anti-earthquake research on it.Firstly,modal analysis was performed using the finite element analysis method to determine that the natural frequency of the control valve is greater than 33 Hz.Therefore,the equivalent static method was used for anti-earthquake analysis.Subsequently,stress assessment was carried out for the identified critical areas based on the calculation results,and the results meet the relevant requirements of ASME nuclear power regulations and standards.Finally,anti-earthquake experiments and post-earthquake functional detection experiments were conducted.The results of the anti-earthquake experiments overall match the simulation results,and the post-earthquake functional detection experiment indicates that the control valve did not suffer any damage and can still achieve its intended regulatory function.Both the simulation and experimental results demonstrate that the general non-powered nuclear-grade cage-type control valve can maintain structural integrity and functional stability under seismic conditions.