• 中文核心期刊
  • CSCD中国科学引文数据库来源期刊
  • 中国科技核心期刊
  • 中国机械工程学会材料分会会刊
Advanced Search
YAO Zhen-hua, XIONG Wei-hao, PENG Qian-yun, ZHOU Min. Effects of Pressing Pressure and Sintering Temperature on the Microstructure and Properties of Fe-Cr-W-Ti-Y2O3 Alloy[J]. Materials and Mechanical Engineering, 2011, 35(6): 4-7.
Citation: YAO Zhen-hua, XIONG Wei-hao, PENG Qian-yun, ZHOU Min. Effects of Pressing Pressure and Sintering Temperature on the Microstructure and Properties of Fe-Cr-W-Ti-Y2O3 Alloy[J]. Materials and Mechanical Engineering, 2011, 35(6): 4-7.
shu

Effects of Pressing Pressure and Sintering Temperature on the Microstructure and Properties of Fe-Cr-W-Ti-Y2O3 Alloy

More Information
  • Received Date: March 25, 2011
    Graphical Abstract
    • Abstract
  • The Fe-12Cr-2.5W-0.4Ti-0.3Y2O3 alloy was prepared by powder metallurgy method, and the effects of pressing pressure and sintering temperature on microstructure and properties of the sintered body were studied. The results show that chromium and tungsten atoms had not completely entered into α-Fe in solid solution mode during milling, but complete solid solution could be carried out during sintering. The pressed compact density and bending strength raised with the increase of the pressing pressure and gradually tended to stability after the pressure was up to 700 MPa. The increase of pressing pressure and sintering temperature was advantageous to the raising of the sintered body strength. The sintered body tensile strength was 416.7 MPa when pressing pressure was 700 MPa and sintering temperature was 1 400 ℃, and the fracture mode was ductile fracture.
    • FullText(HTML)
    • References (10)
  • [1]
    UKAI S, HARADA M, OKADA H, et al. Tube manufactu-ring and mechanical properties of oxide dispersion strengthened ferritic steel[J].Journal of Nuclear Materials, 1993, 204:74-80.
    [2]
    UKAI S, HARADA M, OKADA H, et al. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials[J].Journal of Nuclear Materials, 1993, 204:65-73.
    [3]
    UKAI S, FUJIWARA M. Perspective of ODS alloys application in nuclear enviorments[J].Journal of Nuclear Materials, 2002, 307/311(1):749-751.
    [4]
    UKAI S, OHTSUKA S. Low cycle fatigue properties of ODS ferritic-martensitic steels at high temperature[J].Journal of Nuclear Materials, 2007, 367/370(1):234-238.
    [5]
    KIM I S, HUNN J D, HASHIMOTO N. Defect and void evolution in oxide dispersion strengthened ferritic steels under 3.2 MeV Fe+ ion irradiation with simultaneous helium injection[J].Journal of Nuclear Materials, 2000, 280(3):264-274.
    [6]
    KIMURA A, SUGANO R, MATSUSHITA Y, et al. Thermal helium desorption behavior in advanced ferritic steels[J].Journal of Physics and Chemistry of Solids, 2005, 66(2/4):504-508.
    [7]
    KLEUEH R L, HARRIES D R. High-chromium ferritic and martensitic steels for nuclear application[M].American: ASTM International, 2001.
    [8]
    LEE J H, KASADA R, CHO H S, et al. Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels[J].Journal of ASTM International, 2009, 6(8):164-175.
    [9]
    OLIER P, OKSIUTA Z, MELAT J F, et al. Microstructure and cold workability assessment of a new ODS ferritic steel[J].Advanced Materials Research, 2009, 59:312-318.
    [10]
    姚振华, 熊惟皓, 宋妮, 等.机械合金化Fe-Cr-W-Ti-Y-(O)粉末特性[J].华中科技大学学报: 自然科学版, 2010, 38(3):20-24.
    • Related Articles

Catalog

    Get Citation
    PDF
    XML
    Article views (3) PDF downloads (0) Cited by()
    Turn off MathJax
    Article Contents
    Abstract
    References

    Materials and Mechanical Engineering

    Address：99 Handan Road, ShanghaiPost Code: 200437

    Tel：021-65556775-368Email:mem@mat-test.com

    沪ICP备17055736号-5

    Supported by: Beijing Renhe Information Technology Co., Ltd.  Baidu Analytics

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return