欢迎登录材料期刊网

材料期刊网

高级检索

采用非自耗真空电弧熔炼方法制备Zr-0.4Fe-1.0Cr-xMo (x=0,0.2,0.4,0.6)合金材料,研究了该锆合金在室温下及350℃下的拉伸性能.Zr-0.4Fe-1.0Cr-xMo合金的强度高于Zr-1.0Sn-0.3Nb-0.3Fe-0.1Cr合金.室温下,合金的抗拉伸强度随着Mo含量的增加而降低,而350℃下,合金的抗拉伸强度随着Mo含量的增加而升高,Mo对Zr-0.4Fe-l.0Cr合金有明显的高温强化作用.形变强化指数n值随Mo含量的变化趋势与屈服强度的变化趋势相反.Mo含量对Zr-0.4Fe-l.0Cr-xMo合金拉伸性能的影响与Mo的添加引起第二相粒子特征的变化密切相关.

参考文献

[1] Chunwen Sun;Rob Hui;Wei Qu et al.[J].Corrosion Sience,2009,51:2508.
[2] Arthur T Motta;Aylin Yilmazbayhan;Gomes da Silva et al.[J].Journal of Nuclear Materials,2007,371:61.
[3] Li Qiang;Zhou Bangxin;Yao Meiyi et al.[J].Rare Metal Materials and Engineering(稀有金属材料与工程),2007,36(08):1358.
[4] Wang Jun;Long Chongsheng;Xiong Ji et al.[J].Nuclear Power Engineering(核动力工程),2009,30(05):58.
[5] Chun Y B;Hwang S K;Kim M H et al.[J].Journal of Nuclear Materials,1999,265:28.
[6] Isobe T;Matsuo Y.Zirconium in the Nuclear Industry[M].Philadelphia:ASTM,1991:346.
[7] Pahutova M;Cadek J .[J].Material Science and Engineering,1975,20:277.
[8] Charity I;Murty K L .[J].Journal of Nuclear Materials,2008,374:354.
[9] George P Sabol;Robert J Comstock;Umesh P Nayak.Zirconium in The Nuclear Industry[M].Philadelphia:ASTM,2000:525.
[10] Chun Y B;Hwang S K;Kwun S I et al.[J].Scripta Materialia,1999,40(10):1165.
[11] Lee JH.;Yasuda K.;Kinoshita C.;Hwang SK. .Effect of molybdenum on electron radiation damage of Zr-base alloys[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2001(3):334-337.
[12] Lee JH.;Hwang SK. .Effect of Mo addition on the corrosion resistance of Zr-based alloy in water containing LiOH[J].Journal of Nuclear Materials: Materials Aspects of Fission and Fusion,2003(2/3):238-248.
[13] Pan Jinsheng;Tong Jianmin;Tian Minbo.Fundaments of Materials Science[M].北京:清华大学出版社,2009:589.
[14] Peng Qian;Shen Baoluo .[J].Rare Metals(稀有金属),2005,29(06):903.
[15] Shu Delin.Mechanical Properties of Engineering Materials[M].Beijing:Mechanical Industry Press,2003:18.
上一张 下一张
上一张 下一张
计量
  • 下载量()
  • 访问量()
文章评分
  • 您的评分:
  • 1
    0%
  • 2
    0%
  • 3
    0%
  • 4
    0%
  • 5
    0%