Tensile Behavior of High Temperature Cu-Cr-Zr Alloy

被引：0
作者：
Zhang, X. W. [1 ]
Zhou, X. [1 ]
Wang, Q. J. [1 ]
Liang, B. [1 ]
机构：
[1] Xian Univ Architecture & Technol, Sch Met & Engn, Xian, Peoples R China
来源：
PROCEEDINGS OF THE 2015 INTERNATIONAL CONFERENCE ON POWER ELECTRONICS AND ENERGY ENGINEERING (PEEE 2015) | 2015年 / 20卷
关键词：
Cu-Cr-Zr alloy; tensile properties; high temperature; fracture pattern; MICROSTRUCTURE; DEFORMATION; DUCTILITY;
D O I：
暂无
中图分类号：
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号：
0807 ; 0820 ;
摘要：
The tensile behavior of Cu-Cr-Zr alloy was investigated at different temperatures. The material investigated was heat treated to the following condition: solutionizing 980 degrees C-40 min then water quenching, aging 460 degrees C-4 h. The test temperature was ranged from room temperature to 600 degrees C at intervals of 100 degrees C. Curves describing the tensile properties were obtained. The Vickers hardness, microstructure and fracture surface of the tested alloys were also studied. The results reveal that the tensile strength of Cu-Cr-Zr alloys decreases with the increase of temperatures. Additionally, due to fully recrystallization, a combination of a high tensile strength with a fairly good plasticity can be achieved at 200 degrees C. The suitable working temperature of Cu-Cr-Zr alloy ranges form room temperature to 300 degrees C. The results also indicate that the mechanism of Cu-Cr-Zr alloy fracture is the nucleation, growth, extension and join of microvoid caused by second phase particle.
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页码：191 / 194
页数：4
相关论文
共 18 条
  • [1] Specification of CuCrZr alloy properties after various thermo-mechanical treatments and design allowables including neutron irradiation effects
    Barabash, V. R.
    Kalinin, G. M.
    Fabritsiev, S. A.
    Zinkle, S. J.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) : 904 - 907
  • [2] Microstructure and properties of a Cu-Cr-Zr alloy
    Batra, IS
    Dey, GK
    Kulkarni, UD
    Banerjee, S
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2001, 299 (02) : 91 - 100
  • [3] Material properties and design requirements for copper alloys used in ITER
    Davis, JW
    Kalinin, GM
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1998, 258 : 323 - 328
  • [4] Evaluation of copper alloys for fusion reactor divertor and first wall components
    Fabritsiev, SA
    Zinkle, SJ
    Singh, BN
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 127 - 137
  • [5] Heat treatment of CuCrZr cooling tubes for JT-60SA monoblock-type divertor targets
    Higashijima, S.
    Sakurai, S.
    Sakasai, A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) : 912 - 915
  • [6] Huang FX, 2003, SCRIPTA MATER, V48, P97, DOI 10.1016/S1359-6462(02)00353-6
  • [7] Grain refinement in CuCrZr by SPD processing
    Kulczyk, Mariusz
    Zysk, Beata
    Lewandowska, Malgorzata
    Kurzydlowski, Krzysztof J.
    [J]. PHYSICA STATUS SOLIDI A-APPLICATIONS AND MATERIALS SCIENCE, 2010, 207 (05): : 1136 - 1138
  • [8] Thermal stability of heavily drawn Cu-0.4 wt.%Cr-0.12 wt.%Zr-0.02 wt.%Si-0.05 wt.%Mg
    Li, X. F.
    Dong, A. P.
    Wang, L. T.
    Yu, Z.
    Meng, L.
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 2011, 509 (10) : 4092 - 4097
  • [9] The stored energy in processed Cu-0.4 wt.%Cr-0.12 wt.%Zr-0.02 wt.%Si-0.05 wt.%Mg
    Li, X. F.
    Dong, A. P.
    Wang, L. T.
    Yu, Z.
    Meng, L.
    [J]. JOURNAL OF ALLOYS AND COMPOUNDS, 2011, 509 (14) : 4670 - 4675
  • [10] Effects of Cr and Zr additions on the microstructure and properties of Cu-6 wt.% Ag alloys
    Liu, J. B.
    Zhang, L.
    Dong, A. P.
    Wang, L. T.
    Zeng, Y. W.
    Meng, L.
    [J]. MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2012, 532 : 331 - 338
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