一种量化核燃料降解和裂变产物影响的机器学习方法

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Denise A. Lopes, Rinkle Juneja, Alicia M. Raftery, J. Matthew Kurley, William F. Cureton, Andrew T. Nelson
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引用次数: 0

摘要

核燃料的性能取决于对运行条件下燃料性能演变的理解,这是一项由裂变过程中的化学变化和大量辐射损伤驱动的复杂挑战。传统上,性质演变是通过辐照后收集的经验数据来确定的。然而,这些经验相关性在超出获得它们的特定条件的适用性方面是有限的。本研究通过应用材料信息学开发机器学习随机森林(ML-RF)模型来探索解决这一挑战的新方法,该模型可以捕获裂变产物对燃料化合物的影响。该模型通过利用广泛的量子材料特性数据并将其与材料描述符(如组成、原子和位点特征以及晶格特性)相关联来预测形成焓(ΔHf)。该ML-RF模型能够在训练数据覆盖的成分和结构空间中快速插值,从而支持高通量筛选和候选阶段的能量排序。该模型证明了预测ΔHf的能力,平均绝对误差(MAE)约为0.1至0.2 eV/原子,适用于广泛的化合物,包括关键的核燃料系统(U-O, U-N, U-C, U-Si和U-Mo)。例如,它被用于评估UO2 (O/M)和UN (N/M)燃料的化学计量变化,揭示了它们在化学势变化方面的不同趋势,并实现了初步的凸包分析。此外,该模型还提供了对单个裂变产物如何影响燃料特性的见解。结果表明,较大的裂变产物(如Nd、Pu、Ce)对UO2的影响更为明显,而较轻的裂变产物(如Zr)对UN的影响较强。在这项工作中开发的模型可用于支持加速燃料鉴定方法,在广泛的材料建模和实验之前促进初步评估。为此目的,已向燃料界提供经过培训的模型,以支持正在进行的燃料开发工作。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
A machine learning approach to quantify degradation of nuclear fuels and the effects of fission products
Nuclear fuel performance is critically dependent on understanding the evolution of fuel properties under operational conditions, a complex challenge driven by chemical changes and substantial radiation damage during fission. Traditionally, property evolution has been determined via empirical data collected following irradiation. However, these empirical correlations are limited in their applicability beyond the specific conditions in which they were obtained. This study explores a novel approach to address this challenge by applying materials informatics to develop a machine learning random forest (ML-RF) model that captures the effects of fission products on fuel compounds. The model predicts formation enthalpy (ΔHf) by leveraging extensive quantum materials property data and correlating it with material descriptors such as composition, atomic and site features, and crystal lattice properties. This ML-RF model enables rapid interpolation across the compositional and structural spaces covered by the training data, thus supporting high-throughput screening and energetic ranking of candidate phases. The model demonstrates the ability to predict ΔHf with a mean absolute error (MAE) of approximately 0.1 to 0.2 eV/atom across a wide range of compounds, including key nuclear fuel systems (U-O, U-N, U-C, U-Si, and U-Mo). For example, it was used to assess shifts in stoichiometry for UO2 (O/M) and UN (N/M) fuels, revealing their distinct tendencies in chemical potential variation and enabling preliminary convex hull analyses. Furthermore, the model provides insights into how individual fission products affect fuel properties. Results indicate that larger fission products (e.g., Nd, Pu, Ce) have a more pronounced impact on UO2, while lighter ones (e.g., Zr) strongly influence UN. The model developed in this work can be used to support the Accelerated Fuel Qualification approach by facilitating preliminary evaluations prior to extensive materials modeling and experimentation. To this end, the trained model has been made available to the fuel community to support ongoing fuel development efforts.
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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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