核主泵机械密封故障溯源方法与验证

Abnormity Attribution Method and Verification for Mechanical Seal of Reactor Coolant Pump

  • 摘要: 核主泵机械密封受结构限制而无法得到足够的监测信息,导致系统物理模型处于欠定义状态而无法求得定解,即不同部件(密封、节流盘管)的不同特性参数变化可能导致相近的监测结果无法区分。本文提出一种基于概率模型的分析算法,用于在机械密封运行中实时分析其健康状态、发生故障时及时报警并分析其原因。此方法以最大似然系统状态和故障事件概率两种形式给出分析结果。前者推算具有最大概率密度的密封、节流盘管特性参数,并重构系统状态;后者基于采样对用户关注的指定事件计算概率。采用某核电机组约1年时长的真实分压、流量数据对方法进行了检验,发现本文方法得到的结果与停机检修结论及真实监测所得的总低压泄漏量具有较好的一致性。这表明本文方法可有效对核主泵机械密封进行健康监测和故障溯源,具有较高的推广价值。

     

    Abstract: Mechanical seals are widely used in nuclear power equipment, and the analysis on their abnormities received a lot of attention. The reactor coolant pump focused in the presented study is composed with three seals and four throttles. Linear models for the seals and the throttles were established for efficient computation, the parameters on the designed state were determined according to operating condition and related literature. Discussions on the fluid resistance impact to the seal system show that the monitored information is inadequate for a definite solution of the reactor coolant pump mechanical seal physical model, namely forming an underdefined problem. That is, different characteristic parameters of the components may lead to similar monitored results and thus cannot be distinguished. This is due to the structure of the mechanical seal system of the reactor coolant pumps, and cannot be easily changed for current users of the pumps. Probabilitybased algorithms were proposed to provide realtime analysis for the health status of seal, thus to alarm and find the cause when abnormity exists. The parameters in the characteristic models of the seals and the throttles were assumed to obey Gaussian distributions which have mean values corresponding to the designed state and standard deviations decided by the flux magnitudes. The results were given in the forms of maximum likelihood state and the abnormity event probability, respectively. The maximum likelihood characteristic parameters were calculated based on the probability density function of the prior distribution, and then the corresponding full description of the system state was generated, providing an intuitive illustration of the multistage seal system including the probable abnormity causes and the flux through each of the seals and the throttles. By sampling according to the prior distribution and defining a fuzzy selection rule, the probability of the specified events concerned by the user was obtained through Bayesian principle. Three thresholds of different severity levels were configured for each of the seals in the system and the probability of abnormity beyond the thresholds were analyzed. The methods were tested on an about oneyearduration real operation dataset containing pressure and flow rate data of three pumps in a reactor coolant system, and it is found that the result of the methods is consistent with the conclusion drawn in shutdown maintenance and the monitored total leakage of the three pumps in a reactor coolant, indicating that the method can effectively attributes the abnormity of the multistage mechanical seal system of reactor coolant pumps. This shows that the method can effectively carry out health monitoring and fault tracing for the mechanical seal of reactor coolant pump, and it has high popularization value.

     

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