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UNCERTAINTY ASSESSMENT OF COMPONENT DEGRADATION MODEL BASED ON SUPPORT VECTOR REGRESSION

机译:基于支持向量回归的组件退化模型的不确定度评估

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Degradation modeling and condition assessment of critical components are important issues in the maintenance of nuclear power plant, but modeling uncertainties must be taken into account seriously by considering the stochastic nature of degradation and observation process. Based on support vector regression algorithm, this article proposes a wall thinning model for carbon steel pipes in a nuclear power plant using in-service inspections data and further performs the uncertainty quantitive assessment for the proposed model. In the beginning, Latin hypercube sampling method is used to create new sample sets from the original observation with certain distribution of the mean values which are assumed from the observed data. Furthermore, part of the reconstructed sample sets are chosen as training sets to develop a wall thinning model and the remaining samples are used as test sets to verify the model. By comparing model predicted wall thickness values of the test sets and the observed values, a quantitative assessment of the degradation model uncertainty is obtained. The obtained results demonstrate that the deviations between observed thickness values and average model predicted values fluctuate around 1%, while model predicting variances are much smaller than the observed variances. This report concludes that the proposed support vector regression model for component degradation can provide accurate condition assessments with rather small variance.
机译:退化模型和关键部件的状态评估是核电厂维护中的重要问题,但是必须通过考虑退化和观测过程的随机性来认真考虑建模的不确定性。基于支持向量回归算法,本文利用在役检查数据,提出了核电厂碳钢管壁薄化模型,并对该模型进行了不确定性定量评估。首先,使用拉丁超立方体采样方法从原始观测值创建新的样本集,并根据观测数据假定平均值的一定分布。此外,部分重建的样本集被选作训练集以开发壁变薄模型,其余样本被用作测试集以验证模型。通过将测试集的模型预测壁厚值与观察值进行比较,可以获得对退化模型不确定性的定量评估。获得的结果表明,观测到的厚度值与平均模型预测值之间的偏差波动在1%左右,而模型预测的方差比观察到的方差小得多。该报告得出的结论是,提出的用于部件退化的支持向量回归模型可以提供准确的状态评估,且方差很小。

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