Data assimilation for accelerated development of fuel performance codes: Towards automatic implementation of material properties correlations

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-06-10 DOI:10.1016/j.jnucmat.2025.155954

Giovanni Nicodemo , Giovanni Zullo , Antonio Cammi , Lelio Luzzi , Davide Pizzocri

引用次数: 0

Abstract

Developing fuel performance codes requires lengthy technical and legal verification procedures. This work proposes an approach to automate and facilitate these processes by using a data assimilation method. The method considered is Gaussian process regression, which allows for exploiting experimental data to correct/update material property correlations in fuel performance codes. As a demonstration of this method, the correlation for the single-atom xenon diffusivity is updated in the SCIANTIX code with recent lower-length scale results, without the need to modify the SCIANTIX code itself. The goal is to demonstrate the validity of this approach for data-driven developments of physics-based fuel performance codes.

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加速燃料性能代码开发的数据同化：迈向材料特性相关性的自动实现

制定燃油性能规范需要漫长的技术和法律验证程序。这项工作提出了一种通过使用数据同化方法来自动化和简化这些过程的方法。所考虑的方法是高斯过程回归，它允许利用实验数据来纠正/更新燃料性能代码中的材料属性相关性。作为该方法的演示，在SCIANTIX代码中更新了单原子氙扩散率的相关性，并使用了最近的低长度尺度结果，而无需修改SCIANTIX代码本身。目的是证明这种方法在数据驱动的基于物理的燃料性能代码开发中的有效性。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.