反应堆控制棒失步故障诊断系统设计  被引量:1

Design on Fault Diagnosis System for Reactor Control Rod out of Step

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作  者:巴少华 夏虹[1] 王武[1] BA Shaohua;XIA Hong;WANG Wu(Nuclear Safety iind Advanced Nuclear Energy Key laboratory,Harbin Engineering University,Harbin 150001,China)

机构地区:[1]哈尔滨工程大学核安全与先进核能技术重点实验室,黑龙江哈尔滨150001

出  处:《自动化仪表》2021年第10期102-105,110,共5页Process Automation Instrumentation

摘  要:反应堆控制棒棒位与堆芯的总功率息息相关。而在反应堆运行过程中,无法直接观测到控制棒是否发生失步故障;同时,传统的故障诊断方法无法针对该故障进行定位因此,需要通过其他方法对控制棒失步进行状态监测与故障诊断。以秦山一期反应堆堆芯为研究对象,利用REMARK仿真程序计算得到堆内三个不同位置的中子计数。采用阈值检测法进行状态监测,并通过反向传播(BP)神经网络进行故障诊断。使用MCNP5模拟的故障数据进行仿真验证。验证结果表明,该系统能够在不同的工况下,较好地诊断出反应堆控制棒失步的故障定位与故障程度,实现了对控制棒失步故障在线实时监测与诊断,能够为操作员提供相应的故障信息,提高了反应堆的安全性能。The position of reactor control rod is closely related to the total power of the core.Il is impossible to directly observe whether control rods have out-of-step faults during the operation of the reactor.At the same time,the traditional fault diagnosis methods cannot locate the faults.Therefore,other methods are needed to monitor and diagnose the control rod out-of-step.Taking the Qinshan Phase I reactor core as the research object,the fault data is simulated and verified with REMARK simulation program to calculate the neutron counts at three different positions in the reactor,the condition is niornitored by using the threshold detection method,and the fault is diagnosed by back propagation(BP)neural network.The MCNP5 simulation is used to simulate and verigy the fault data.The verification results show that the system can better diagnose the fault location and fault degree of reactor control rod out-of-step under different working conditions,and can realize the online real-time monitoring and diagnosis of the control rod out-of-step fault.This can provide operators with corresponding fault information.The safety performance of the reactor can be improved.

关 键 词:控制棒失步 反向传播神经网络 状态监测 故障诊断 阈值检测法 故障定位 中子计数 反应堆堆芯 

分 类 号:TH86[机械工程—仪器科学与技术]

 

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