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理解六方密堆积结构锆多晶体中的氢化物析出机制:一种微观力学方法。

Understanding the hydride precipitation mechanism in HCP Zr polycrystals: a micromechanical approach.

作者信息

Liu Yang, Wenman Mark R, Davies Catrin M, Dunne Fionn P E

机构信息

Department of Materials, Imperial College London, London, SW7 2AZ UK.

School of Engineering, University of Leicester, Leicester, LE1 7RH UK.

出版信息

J Mater Sci. 2025;60(14):6254-6287. doi: 10.1007/s10853-025-10796-8. Epub 2025 Apr 10.

DOI:10.1007/s10853-025-10796-8
PMID:40260010
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC12009237/
Abstract

This study focuses on the hydride precipitation in zirconium polycrystals during thermo-mechanical cycles. The precipitation and dissolution of mesoscale hydrides in Zircaloy-4 is modelled using crystal plasticity finite element methods supported with DFT-informed zirconium lattice hydrogen concentration. Results for a tri-crystal case show the effects of crystallography, thermo-mechanical load and elasto-plastic anisotropy on hydride nucleation and growth. Analyses of polycrystalline models provide new insights into the complex precipitation process of hydrides in Zircaloy-4 with explicit representation of experimental observations that lay the foundation for further research in this field. Micromechanical findings demonstrate the importance of microstructure, pre-thermal condition, and hydrogen concentration limit on hydride precipitation. Overall, the study provides a deeper understanding of hydride formation during industrially relevant reactor conditions.

摘要

本研究聚焦于热机械循环过程中锆多晶体中的氢化物析出。采用晶体塑性有限元方法,并结合基于密度泛函理论(DFT)的锆晶格氢浓度,对锆合金-4中细观尺度氢化物的析出和溶解进行建模。三晶体案例的结果显示了晶体学、热机械载荷和弹塑性各向异性对氢化物形核和生长的影响。多晶体模型分析为锆合金-4中氢化物复杂的析出过程提供了新见解,明确呈现了实验观察结果,为该领域的进一步研究奠定了基础。微观力学研究结果表明微观结构、预热条件和氢浓度极限对氢化物析出的重要性。总体而言,该研究加深了对工业相关反应堆条件下氢化物形成的理解。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/7293be4f133d/10853_2025_10796_Fig22_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/cb1cfd47ad8b/10853_2025_10796_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/555a398c642c/10853_2025_10796_Fig15_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/4de35179db7f/10853_2025_10796_Fig16_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/bf2ea2e3bfb0/10853_2025_10796_Fig17_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/e539fd41db5d/10853_2025_10796_Fig18_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/627fa7e8451e/10853_2025_10796_Fig19_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/e895c3a94236/10853_2025_10796_Fig20_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/742789a7c5ef/10853_2025_10796_Fig21_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/7293be4f133d/10853_2025_10796_Fig22_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/cb1cfd47ad8b/10853_2025_10796_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/555a398c642c/10853_2025_10796_Fig15_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/4de35179db7f/10853_2025_10796_Fig16_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/bf2ea2e3bfb0/10853_2025_10796_Fig17_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/e539fd41db5d/10853_2025_10796_Fig18_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/627fa7e8451e/10853_2025_10796_Fig19_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/e895c3a94236/10853_2025_10796_Fig20_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/742789a7c5ef/10853_2025_10796_Fig21_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b161/12009237/7293be4f133d/10853_2025_10796_Fig22_HTML.jpg

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本文引用的文献

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Sample container for high-resolution neutron imaging of spent nuclear fuel cladding sections.用于乏核燃料包壳段高分辨率中子成像的样品容器。
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Quantification Challenges for Atom Probe Tomography of Hydrogen and Deuterium in Zircaloy-4.锆合金-4中氢和氘的原子探针层析成像的定量挑战
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