基滑对Zr702锆合金塑性变形行为的重要性

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2025-01-24 DOI:10.1016/j.jnucmat.2025.155655
X. Chen , A. Chapuis , W.J. He , Q. Liu
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引用次数: 0

摘要

采用实验和粘塑性自洽(VPSC)模拟方法研究了轧制Zr702锆板的塑性变形行为。在室温下,沿RD、TD和ND(分别为滚动、横向和法线方向)进行压缩试验,并测量塑性各向异性(r值或兰克福德系数)。EBSD测量用于评估10%应变压缩后的初始织构和孪晶体积分数。压缩应力-应变曲线用于拟合棱柱滑移、基滑移和< c + a >滑移的临界分解剪切应力(CRSS),并拟合{10-12}张力孪晶的临界分解剪切应力(CRSS)以重现所测孪晶体积分数。我们发现基底滑移是再现塑性流动各向异性所必需的,但应力应变曲线可以用多组材料参数再现。提出了两组材料参数:第一组基面滑移的CRSS等于锥体< c + a >滑移的CRSS,第二组基面滑移的CRSS是< c + a >滑移的一半。预测的塑性应变各向异性(r值)在很大程度上取决于基底滑移的CRSS。模拟结果表明,只有当基底滑移的CRSS为< c + a >滑移的一半时,预测r值才与实验值相符。另一个自洽模型证实了基底滑动的CRSS是< c + a >滑动的一半。滑迹分析证实了基底滑移和锥体< c + a >滑移的激活,锥体< a >滑移可能被激活。采用不同的材料参数对平面应变变形后的织构进行了预测,结果表明,平面应变变形后的织构非常相似。
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Importance of basal slip on the plastic deformation behavior of zirconium alloy Zr702
The plastic deformation behavior of a rolled Zr702 zirconium plate is investigated experimentally and with visco-plastic self-consistent (VPSC) simulations. Compression tests along the RD, TD and ND (rolling, transverse and normal directions, respectively) are done at room temperature and the plastic anisotropy (r-values or Lankford coefficients) is measured. EBSD measurements are used to assess the initial texture and the twin volume fraction after 10 % strain compression. Compression stress-strain curves are used to fit the critical resolved shear stress (CRSS) for prismatic, basal and 〈c + a〉 slip, and the CRSS for {10–12} tension twinning is fitted to reproduce the measured twin volume fraction. We found that basal slip is necessary to reproduce the plastic flow anisotropy, but stress strain curves can be reproduced with several sets of material parameters. Two set of material parameters are presented: first with the CRSS for basal slip equal to the CRSS for pyramidal 〈c + a〉 slip, second with the CRSS for basal slip half that for 〈c + a〉 slip. The predicted plastic strain anisotropy (r-value) strongly depends on the CRSS for basal slip. Simulations proved that the predicted r-values match the experimental ones only when the CRSS for basal slip is half that of 〈c + a〉 slip. Another self-consistent model is used to confirm that the CRSS for basal slip is half that of 〈c + a〉 slip. Slip traces analysis confirmed the activation of basal slip and pyramidal 〈c + a〉 slip, and pyramidal 〈a〉 slip was possibly activated. The different material parameters are used to predict the texture after plane strain deformation and simulations show that the textures are quite similar.
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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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