稀Zr-2.5Nb-Y合金组织演变及氢化行为研究

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Y. Pushpalatha Devi , K.V. Mani Krishna , N. Keskar , J.B. Singh , R.N. Singh
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引用次数: 0

摘要

Zr-2.5Nb合金是重水堆的关键压力管材料,其性能直接影响堆的使用寿命和安全性。然而,这种合金中氢化物的形成会对其机械性能产生不利影响。在本研究中,钇被用作稀释添加剂来减轻氢化物脆。制备了钇含量为0.5 ~ 2%的合金。添加钇可形成细小的钇析出物。与参考合金Zr2.5Nb相比,含Y合金的热变形显微组织在相形态和先前β相分数方面存在显著差异。膨胀法研究表明,钇的加入降低了合金的β-透射温度。合金的氢化物行为也被检测到,与不含钇(Zr-2.5Nb)时10-150 μm的氢化物尺寸相比,钇显著降低到20 μm的氢化物尺寸。通过在Zr-2.5Nb合金中添加钇,对合金的微观组织和氢化行为进行了综合研究,表明可以考虑添加钇来改善合金在核应用中的性能,以减轻氢化物脆化。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
On the microstructural evolution and hydriding behavior of dilute Zr-2.5Nb-Y alloys
Zr-2.5Nb alloy is a critical pressure tube material in pressurized heavy water reactors (PHWRs), as its performance directly influences the operational life and safety of the reactor. However, the formation of hydrides in this alloy can detrimentally affect its mechanical properties. In the present study, yttrium was employed as a dilute addition to mitigate hydride embrittlement. Alloys were prepared with varying yttrium contents of 0.5 to 2 wt %. Yttrium addition resulted in the formation of fine yttria precipitates. The hot deformed microstructures of alloys with Y exhibited significant differences in morphology of the phases and prior β phase fraction when compared to reference Zr2.5Nb alloy. Dilatometry studies indicated that yttrium addition led to a reduction in the β-transus temperature of the alloy. The hydride behavior of the alloys was also examined, showing that yttrium significantly reduced hydride size to <20 μm, compared to a range of 10–150 μm in the absence of yttrium (Zr-2.5Nb). This comprehensive study of the microstructure and hydriding behavior, with the addition of yttrium to the Zr-2.5Nb alloy, suggests that yttrium may be considered for improving the alloy's performance in nuclear applications, in view of the mitigation of hydride embrittlement.
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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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