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    刘丹华, 谌继明, 吴继红, 闫得胜. 国际热核实验堆第一壁材料CuCrZr合金及其与不锈钢焊接接头的力学性能[J]. 机械工程材料, 2009, 33(3): 46-49.
    引用本文: 刘丹华, 谌继明, 吴继红, 闫得胜. 国际热核实验堆第一壁材料CuCrZr合金及其与不锈钢焊接接头的力学性能[J]. 机械工程材料, 2009, 33(3): 46-49.
    shu
    LIU Dan-hua, CHEN Ji-ming, WU Ji-hong, YAN De-sheng. Mechanical Properties of the CuCrZr Alloy and CuCrZr/SS Joints for ITER First Wall[J]. Materials and Mechanical Engineering, 2009, 33(3): 46-49.
    Citation: LIU Dan-hua, CHEN Ji-ming, WU Ji-hong, YAN De-sheng. Mechanical Properties of the CuCrZr Alloy and CuCrZr/SS Joints for ITER First Wall[J]. Materials and Mechanical Engineering, 2009, 33(3): 46-49.
    shu

    国际热核实验堆第一壁材料CuCrZr合金及其与不锈钢焊接接头的力学性能

    Mechanical Properties of the CuCrZr Alloy and CuCrZr/SS Joints for ITER First Wall

      摘要
    • 摘要: 将经过真空熔炼、铸造、热轧后的国际热核实验堆(ITER)第一壁中所使用的CuCrZr合金进行960～1 040 ℃固溶处理后,分别在475 ℃和580 ℃进行时效处理;对CuCrZr合金的力学性能进行测试,对显微组织进行观察;将CuCrZr合金与316L不锈钢进行热等静压(HIP)焊接,对焊接接头组织与性能进行了研究.结果表明:该合金经时效处理后硬度和强度较固溶态都有明显的提高,尤其是475 ℃保温3 h的时效强化效果最为明显,但合金晶粒发生了明显的长大,伸长率也明显降低.CuCrZr合金和316L不锈钢焊接接头性能良好,但在界面附近的晶粒尺寸差别较大,同时还有脆性相析出.

       

      Abstract: The CuCrZr alloy using for the international thermonuclear experimental reactor (ITER) first wall was prepared by vaccum melting,casting and hot-rolling.The alloys were solid solution annealed at 960-1 040 ℃,then aged at 475 ℃ and 580 ℃ respectively.The tensile properties and microstructure of CuCrZr alloys were investigated.The microstructure and properties of the joints between CuCrZr alloy and 316L stainless steel by hot isostatic press (HIP) method were analyzed.The results show that the hardness and strength of the alloy improved after aging,especially aging at 475 ℃ for 3 h.However it had larger grain size,and the elongation decreased obviously.The properties of the joints were good,and the grain size had significant difference near the interface.And some had phases precipitated.

       

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