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Characterization of used nuclear fuel with multivariate analysis for process monitoring

机译:使用多变量分析表征废旧核燃料以进行过程监控

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This paper presents initial development of a reactor-type classifier that is used to select a reactor-specific partial least squares model to predict used nuclear fuel burnup. Nuclide activities for prototypic used fuel samples were generated in ORIGEN-ARP and used to investigate techniques to characterize used nuclear fuel in terms of reactor type (pressurized or boiling water reactor) and burnup. A variety of reactor type classification algorithms, including k-nearest neighbors, linear and quadratic discriminant analyses, and support vector machines, were evaluated to differentiate used fuel from pressurized and boiling water reactors. Then, reactor type-specific partial least squares models were developed to predict the burnup of the fuel. Using these reactor type-specific models instead of a model trained for all light water reactors improved the accuracy of burnup predictions. The developed classification and prediction models were combined and applied to a large dataset that included eight fuel assembly designs, two of which were not used in training the models, and spanned the range of the initial ~(235)U enrichment, cooling time, and burnup values expected of future commercial used fuel for reprocessing. Error rates were consistent across the range of considered enrichment, cooling time, and burnup values. Average absolute relative errors in burnup predictions for validation data both within and outside the training space were 0.0574% and 0.0597%, respectively. The errors seen in this work are artificially low, because the models were trained, optimized, and tested on simulated, noise-free data. However, these results indicate that the developed models may generalize well to new data and that the proposed approach constitutes a viable first step in developing a fuel characterization algorithm based on gamma spectra.
机译:本文介绍了一种反应堆类型分类器的初步开发,该分类器用于选择特定于反应堆的偏最小二乘模型来预测使用过的核燃料燃耗。原型用过的燃料样品的核素活性在ORIGEN-ARP中生成,并用于研究根据反应堆类型(加压或沸水反应堆)和燃耗表征废旧核燃料的技术。评估了各种反应堆类型分类算法,包括k近邻,线性和二次判别分析以及支持向量机,以区分用过的燃料与增压和沸水反应堆。然后,开发了针对反应堆类型的偏最小二乘模型,以预测燃料的燃耗。使用这些特定于反应堆类型的模型,而不是针对所有轻水反应堆训练的模型,可以提高燃尽预测的准确性。将已开发的分类和预测模型组合并应用于包含八个燃料组件设计的大型数据集,其中两个未用于训练模型,并且涵盖了初始〜(235)U富集,冷却时间和未来商业化后处理燃料的燃耗值。在考虑的浓缩,冷却时间和燃耗值的范围内,错误率保持一致。在训练空间内外的验证数据燃耗预测中的平均绝对相对误差分别为0.0574%和0.0597%。在这项工作中看到的错误是人为地降低了,因为模型是在模拟的,无噪声的数据上进行训练,优化和测试的。然而,这些结果表明,所开发的模型可以很好地推广到新数据,并且所提出的方法构成了开发基于伽马光谱的燃料表征算法的可行的第一步。

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