首页> 外文会议>International conference on nuclear engineering >A STATISTICAL MODEL FOR ACCESSING WALL THINNING RATE DUE TO FLOW ACCELERATED CORROSION BASED ON INSPECTION DATA IN NUCLEAR POWER PLANTS
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A STATISTICAL MODEL FOR ACCESSING WALL THINNING RATE DUE TO FLOW ACCELERATED CORROSION BASED ON INSPECTION DATA IN NUCLEAR POWER PLANTS

机译:基于核电厂核查数据的流动加速腐蚀导致壁厚变薄的统计模型

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Flow accelerated corrosion (FAC) is a major degradation form of carbon steel and low alloy pipes in the secondary circuit of pressurized water reactor (PWR) plants, which has great impact on plant safety and reliability. For the purpose of effectively monitoring FAC in nuclear power plants, a statistical model for accessing FAC wall thinning rate using plant inspection data is proposed in this paper. The presented model is developed based on Gaussian stochastic process models. Wall thinning rate is considered as a function of key factors that have important influence on the FAC process (i.e., temperature, pH, mass transfer coefficient, etc.). The Kriging method, which has been widely applied in the domain of spatial analysis, is used to model the relationship between wall thinning rate and its impact factors. Model parameters are determined through maximum likelihood estimation using the inspection data. Since the likelihood function of the Kriging model is usually complicated in form, the genetic algorithm is employed to find parameter values that maximize this function. From the presented model, residual lifetime distributions of pipes affected by FAC can be derived, and conditions that may lead to high FAC rate can be found, which provides decision-making support for maintenance strategies optimization in life cycle management of the feed water system. Wall thinning data simulated from a physical-chemical mechanism model presented in literature are used to verify the presented model. Results of validation show that reasonable wall thinning rates and lifetime distributions can be obtained using this model.
机译:流动加速腐蚀(FAC)是压水堆(PWR)厂二次回路中碳钢和低合金管道的主要降解形式,对工厂安全性和可靠性有很大影响。为了有效监测核电站中的FAC,本文提出了一种使用工厂检查数据获取FAC壁薄率的统计模型。所提出的模型是基于高斯随机过程模型开发的。壁变薄率被认为是对FAC过程具有重要影响的关键因素(即温度,pH,传质系数等)的函数。克里格法已被广泛应用于空间分析领域,它被用来模拟薄壁率及其影响因素之间的关系。使用检查数据通过最大似然估计确定模型参数。由于克里格模型的似然函数通常形式复杂,因此采用遗传算法来查找使该函数最大化的参数值。从提出的模型中,可以得出受FAC影响的管道的剩余寿命分布,并发现可能导致高FAC率的条件,这为给水系统生命周期管理中的维护策略优化提供了决策支持。从文献中提出的物理化学机理模型模拟的壁变薄数据用于验证提出的模型。验证结果表明,使用该模型可以获得合理的壁变薄率和寿命分布。

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