用于预测 316L 不锈钢核包层材料降解的动态数据驱动多尺度模型

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
William E. Frazier, Yucheng Fu, Lei Li, Ram Devanathan
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引用次数: 0

摘要

我们开发了一种长短期记忆堆叠集合(LSTM-SE)代用建模方法,可以快速预测美国钢铁协会(AISI)316L 系列不锈钢(SS316L)燃料包层在不同温度和辐射剂量率条件下的微观结构演变及由此产生的机械性能。为了获取训练数据,我们开发并实施了一个动力学蒙特卡罗(KMC)模型,以模拟 SS316L 包层中 M23C6、γ'和 G 相的析出动力学。文献中报道的 SS316L 实验析出动力学与 KMC 模型中模拟析出的动力学参数相关联。记录析出物的体积分数、数量密度和颗粒大小的变化,并使用统计方法将颗粒面积分数相关联,从而建立代用模型。同时,使用基于微结构的有限元法(FEM)分析评估了模拟微结构的机械性能,以确定老化微结构的弹性模量、屈服应力、极限抗拉强度和伸长率。使用这种方法,我们的代用模型可以在 0.25 % 体积分数的范围内预测析出行为,并使用 50 次训练模拟作为输入,在 6 % 的相对误差范围内预测机械性能,而 KMC 和 FEM 模型预测的值为 0.25 %。训练有素的循环神经网络模型对沉淀动力学和机械性能的估计速度比基于物理的代码快 1000 倍。作为概念验证,这项工作证明了在可获得的数据集的指导下,使用基于统计的模型可以预测变化条件下的微观结构演变。本文讨论了这种建模框架的潜在应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Dynamic data-driven multiscale modeling for predicting the degradation of a 316L stainless steel nuclear cladding material
We have developed a long short-term memory stacked ensemble (LSTM-SE) surrogate modeling approach that can provide rapid predictions of microstructural evolution and the resultant mechanical properties of American Iron and Steel Institute (AISI) 316L series stainless steel (SS316L) fuel cladding under conditions of varying temperature and radiation dose rate. To acquire training data, we developed and implemented a kinetic Monte Carlo (KMC) model to simulate precipitation kinetics of M23C6, γ’, and G phases within SS316L cladding. Experimentally reported precipitation kinetics of SS316L in literature were linked to the kinetic parameters of the simulated precipitation in our KMC model. The model was then used to simulate microstructure evolution under synthetically generated treatments of varying temperature and radiation dose rate for periods of up to 3000 h. Changes in volume fraction, number density, and particle size of precipitates were recorded, and particle area fractions were correlated using statistical methods to develop the surrogate model. Simultaneously, the mechanical properties of the simulated microstructures were evaluated using microstructure-based finite element method (FEM) analysis to determine the elastic modulus, yield stress, ultimate tensile strength, and elongation to failure of the aged microstructures. Using this approach, our surrogate model can predict precipitation behavior within 0.25 % volume fraction and mechanical properties within 6 % relative error from the values predicted by the KMC and FEM models using 50 training simulations as input. The trained recurrent neural network-based model can return estimations of precipitation kinetics and mechanical properties ∼1000 times faster than the physics-based codes. This work demonstrates, as a proof of concept, that microstructural evolution under variable conditions can be predicted using a statistics-based model informed by a practicably obtainable dataset. The potential applications of this type of modeling framework are discussed.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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