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Effect of alloying on the properties of 9Cr low activation martensitic steels

Effect of alloying on the properties of 9Cr low activation martensitic steels
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摘要 Two types of 9Cr low activation martensitic steels (named 9Cr-1 and 9Cr-2) were developed in University of Science and Technology Beijing.9Cr-1 and 9Cr-2 were produced by vacuum induction melting method,and examinations of the microstructures were carried out with X-ray diffraction analysis,optical microscopy,scanning electron microscopy and transmission electron microscopy.The ultimate tensile strength and yield tensile strength were evaluated with tensile tests.The impact properties were characterized with Charpy impact experiments.The results indicated that 9Cr-1 and 9Cr-2 on as-received condition (95 ℃/30 min/water quenching plus 780 ℃/90 min/air cooling) were fully martensitic steels free of δ-ferrite.The ultimate tensile strength of 9Cr-1 and 9Cr-2 were 695 MPa and 680 MPa,respectively.However,9Cr-2 showed a fine grain size of 4.8 μm,and its value of ductile-brittle transition temperature (DBTT) was -90 ℃ under as-received condition.The additions of vanadium,titanium and boron accelerated the formation of MX precipitates and resulted in fine grains and precipitates.The fine grains effectively reduced the value of DBTT from -60 ℃ to -90 ℃ with identical upper shelf energy (USE).The decrease in silicon concentration of 9Cr-2 induced a slight reduction in ultimate tensile strength from 695 MPa to 680 MPa. Two types of 9Cr low activation martensitic steels (named 9Cr-1 and 9Cr-2) were developed in University of Science and Technology Beijing. 9Cr-1 and 9Cr-2 were produced by vacuum induction melting method, and examinations of the microstruc- tures were carried out with X-ray diffraction analysis, optical microscopy, scanning electron microscopy and transmission electron microscopy. The ultimate tensile strength and yield tensile strength were evaluated with tensile tests. The impact properties were characterized with Charpy impact experiments. The results indi- cated that 9Cr-1 and 9Cr-2 on as-received condition (95 ~C/30 min/water quenching plus 780 ~C/90 min/air cooling) were flflly martensitic steels free of ~-ferrite. The ul- timate tensile strength of 9Cr-1 and 9Cr-2 were 695 MPa and 680 MPa, respectively. However, 9Cr-2 showed a fine grain size of 4.8 pm, and its value of ductile-brittle transition temperature (DBTT) was -90 ~C under as-received condition. The additions of vanadium, titanium and boron accelerated the formation of MX precipitates and resulted in fine grains and precipitates. The fine grains effectively reduced the value of DBTT from -60 ℃ to -90 ℃ with identical upper shelf energy (USE). The decrease in silicon concentration of 9Cr-2 induced a slight reduction in ultimate tensile strength from 695 MPa to 680 MPa.
作者 Rong MA Yafeng YANG Qingzhi YAN Ying YANG Xinggang LI Changchun GE Ma, Rong[1];Yang, Yafeng[1];Yan, Qingzhi[1];Yang, Ying[1];Li, Xinggang[1];Ge, Changchun[1];
出处 《金属学报:英文版》 SCIE EI CAS CSCD 2010年第6期451-460,共10页 Acta Metallurgica Sinica(English Letters)
基金 This work was supported by National Basic Research Program of China (No.2007CB209800) and Chinese National Fusion Project for ITER (No.2010G B109000).
关键词 马氏体钢 活化 X射线衍射分析 透射电子显微镜 扫描电子显微镜 合金 性质 北京科技大学 9Cr low activation martensitie steel Grain size Mechanical properties
作者简介 Corresponding author. Professor, PhD: Tel.: +86 13521602959. E-mail address: qingzhiyan111@163.com (Qingzhi YAN)
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参考文献10

  • 1H. Tanigawa,T. Hirose,K. Shiba,R. Kasada,E. Wakai,H. Serizawa,Y. Kawahito,S. Jitsukawa,A. Kimura,Y. Kohno,A. Kohyama,S. Katayama,H. Mori,K. Nishimoto,R.L. Klueh,M.A. Sokolov,R.E. Stoller,S.J. Zinkle. Fusion Engineering and Design . 2008 被引量:1
  • 2T. Hirose,K. Shiba,T. Sawai,S. Jitsukawa,M. Akiba. Journal of Nuclear Materials . 2004 被引量:1
  • 3R.J. Kurtz,A. Alamo,E. Lucon,Q. Huang,S. Jitsukawa,A. Kimura,R.L. Klueh,G.R. Odette,C. Petersen,M.A. Sokolov,P. Sptig,J.W. Rensman. Journal of Nuclear Materials . 2009 被引量:1
  • 4M. Rieth,B. Dafferner,H. D. R¨ohrig. Journal of Nuclear Materials . 1996 被引量:1
  • 5T. Morimura,A. Kimura,H. Matsui. Journal of Nuclear Materials . 1996 被引量:1
  • 6T. Shibayama,A. Kimura,H. Kayano. Journal of Nuclear Materials . 1996 被引量:1
  • 7Y. Kohno,A. Kohyama,T. Hirose,M. L. Hamilton,M. Narui. Journal of Nuclear Materials . 1997 被引量:1
  • 8M. Httestrand,H.O. André. Acta Materialia . 2001 被引量:1
  • 9P. Fernndez,A. M. Lancha,J. Lapen,M. Hernandez-Mayoral. Fusion Engineering and Design . 2001 被引量:1
  • 10E. Girault,A. Mertens,P. Jacques,Y. Houbaert,B. Verlinden,J.V. Hunbeeck. Scripta Materialia . 2001 被引量:1
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