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Microstructures and mechanical properties of the novel CuCrZrFeTiY alloy for fusion reactor
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2020-02-18 , DOI: 10.1016/j.jnucmat.2020.152063
Mingyang Li , Hui Wang , Yuanhang Guo , Hanlu Wang , Dandan Zheng , Jianfu Shan , Yongqin Chang

Cu–Cr–Zr alloy has been widely considered to be used as heat sink materials in the fusion reactor due to its superior properties. However, Cu–Cr–Zr alloy suffers significant creep deformation and softening as the temperatures is above 300–400 °C. Advanced Cu alloys with high strength, high conductivity and high thermal stability need to be developed to meet the requirements in the future fusion reactor. In this work, a novel Cu–Cr–Zr–Fe–Ti–Y alloy was designed and prepared by vacuum induction melting, followed by homogenization treatment, hot-rolled, solid solution, cold-rolled and aging treatments. Tensile properties, hardness and electrical conductivity of the alloys aging at different temperatures were tested. The alloy aged at 500 °C exhibits excellent tensile strength up to 541 MPa and high electrical conductivity of 82% IACS. The alloy maintains high tensile strength even annealing at 500 °C for 72 h. The microstructures of the alloy were characterized by optical, scanning and transmission electron microscopy, and it is found that the high thermal stability of the novel alloy is mainly contributed to two reasons. One is the high friction of low-ΣCSL grain boundaries (mainly Σ3) with low energy detected in the matrix, which are difficult to slid and have higher thermal stability than general high-angle grain boundaries. Another one is the two kinds of high-density precipitates detected in the matrix. The larger Cr1·4Fe particles are semi-coherent with the matrix, and the orientation relationship is [011]Cu//[011]Cr1·4Fe, (100)Cu//(011¯)Cr1·4Fe and (111¯)Cu//(2¯11¯)Cr1·4Fe. The smaller Cr particles are coherent with the matrix, and the orientation relationship is [011]Cu//[1¯11]Cr, (100)Cu//(011¯)Cr and (01¯1)Cu//(211)Cr. The strengthening mechanism of the alloy was analyzed in details, and the calculation yield strength (480 MPa) is well coincident with the experimental value (473 MPa).



中文翻译:

新型聚变反应堆CuCrZrFeTiY合金的组织和力学性能

Cu–Cr–Zr合金由于其优越的性能而被广泛认为是聚变反应堆中的散热器材料。但是,当温度超过300-400 ° C时,Cu-Cr-Zr合金会发生明显的蠕变变形和软化 。需要开发具有高强度,高导电性和高热稳定性的高级Cu合金,以满足未来的熔合要求。反应堆。在这项工作中,通过真空感应熔炼,然后进行均质处理,热轧,固溶,冷轧和时效处理,设计并制备了一种新型的Cu-Cr-Zr-Fe-Ti-Y合金。测试了在不同温度下老化的合金的拉伸性能,硬度和电导率。合金在500 °时效 C表现出高达541 MPa的出色拉伸强度和82%IACS的高电导率。即使在500 ° C退火72 h,该合金也能保持高抗拉强度 。通过光学,扫描和透射电子显微镜对合金的微观结构进行了表征,发现该新型合金的高热稳定性主要归因于两个原因。一种是低ΣCSL晶界(主要是Σ3)的高摩擦力,在基质中检测到的能量较低,与一般的高角度晶界相比,它们难以滑动且具有更高的热稳定性。另一种是在基质中检测到的两种高密度沉淀物。较大的Cr 1·4 Fe颗粒与基体半相干,取向关系为[011]Cu // [011] Cr1·4Fe,(100)Cu //(011个¯Cr1·4Fe和(111个¯//(2¯1个1个¯Cr1·4Fe。较小的Cr颗粒与基体相干,取向关系为[011] Cu // [1个¯11] Cr,(100)Cu //(011个¯Cr和(01个¯1)的Cu //(211)的Cr。详细分析了合金的强化机理,计算出的屈服强度(480 MPa)与实验值(473 MPa)非常吻合。

更新日期:2020-02-20
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