基于Mo-Nb-Ti体系的新型难熔等原子多元素合金的设计

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Anilas Karimpilakkal , Joseph W. Newkirk , Jason L. Schulthess , Frank Liou , Visharad Jalan , Haiming Wen
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引用次数: 0

摘要

多主元素合金(MPEAs)所表现出的优异抗辐照损伤性能引发了研究人员的极大兴趣,促使他们探索其广阔的成分空间,以验证其是否适合核应用。热力学和经验参数计算结合 CALPHAD(CALculation of PHAse Diagrams PHAse Diagrams)进行相形成预测的方法,克服了费力费时的实验,为核等尖端应用实现了高通量材料选择。计算了基于七种低热中子截面难熔元素的八种新型等原子 MPEA 的关键热力学和经验参数,以预测相形成,并采用 CALPHAD 中的平衡和非平衡模拟来全面评估这些系统。伪二元相图模拟显示,在钼铌钛合金(钼铌钛-Zr、钼铌钛-V 和钼铌钛-CrV 合金)基体中添加 Zr、V 或等原子 CrV 有利于在高温下形成同构体心立方(BCC)相、而添加的 Cr、Al、等原子 ZrV 或等原子 CrAl(MoNbTi-Cr、MoNbTi-Al、MoNbTi-ZrV 或 MoNbTi-CrAl 合金)则限制了它们的溶解度。750 °C下的平衡CALPHAD模拟结果与MoNbTi、MoNbTiZr和MoNbTiCr合金的XRD结果一致,其他合金的部分结果也一致。值得注意的是,通过 CALPHAD 中的非平衡谢尔凝固计算,在合金的背散射电子(BSE)扫描电子显微镜(SEM)图像中观察到的元素偏析得到了精确模拟,并通过实验进一步验证。在含 Cr 的 MoNbTiCr 和 MoNbTiCrAl 中,TiCr2 Laves 相的析出得到了准确预测,而在 MoNbTiCrV 中则存在差异。平衡模拟还深入分析了特定温度下的相组成,为定制这些系统所需的微观结构和性能提供了途径。经验参数计算成功地预测了钼铌钛合金基体中的无规固溶,除钼铌钛合金和钼铌钛铝合金外,还预测了其他合金中的金属间析出,尤其是含铬合金中的拉维斯相析出。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design of novel refractory equiatomic multi-principal elemental alloys based on Mo-Nb-Ti system for Gen IV reactor applications
Excellent irradiation damage resistance demonstrated by multi-principal elemental alloys (MPEAs) has sparked significant interest among researchers, prompting exploration into their vast compositional space, to validate their suitability for nuclear applications. A combined approach of thermodynamic and empirical parameters calculations alongside CALPHAD (CALculation of PHAse Diagrams) for phase formation predictions enable high-throughput material selection for sophisticated applications like nuclear, overcoming laborious and time-consuming experiments. Key thermodynamic and empirical parameters for eight novel equiatomic MPEAs, based on seven low thermal neutron cross section refractory elements, for predicting phase formation were calculated, and equilibrium and non-equilibrium simulations in CALPHAD were employed to comprehensively evaluate the systems. Pseudo binary phase diagram simulations showed that Zr, V or equiatomic CrV additions to the base MoNbTi alloy (MoNbTi-Zr, MoNbTi-V and MoNbTi-CrV alloys) favor the formation of isomorphous body-centered cubic (BCC) phase at high temperatures, while Cr, Al, equiatomic ZrV, or equiatomic CrAl additions (MoNbTi-Cr, MoNbTi-Al, MoNbTi-ZrV or MoNbTi-CrAl alloys) limit the solubility of them. Equilibrium CALPHAD simulations at 750 °C were consistent with XRD results on MoNbTi, MoNbTiZr and MoNbTiCr alloys, and partially for others. Notably, elemental segregation observed in the backscattered electron (BSE) scanning electron microscopy (SEM) images of the alloys was accurately simulated through non-equilibrium Scheil solidification calculations in CALPHAD, further verified by experiments. The precipitation of TiCr2 Laves phase in Cr containing MoNbTiCr and MoNbTiCrAl was accurately predicted while discrepancies were noted in MoNbTiCrV. The equilibrium simulations also provided insights into phase compositions at specific temperatures offering a pathway for tailoring the desired microstructure and properties of these systems. Empirical parameters calculations successfully predicted random solid solution in the base MoNbTi alloy, and with an exception in MoNbTiV and MoNbTiAl, predicted intermetallic precipitation in the rest, especially, Laves phase precipitation in Cr containing alloys.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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