期刊文献+

压制压力及烧结温度对Fe-Cr-W-Ti-Y_2O_3合金组织与性能的影响 被引量:2

Effects of Pressing Pressure and Sintering Temperature on the Microstructure and Properties of Fe-Cr-W-Ti-Y_2O_3 Alloy
下载PDF
导出
摘要 采用粉末冶金法制备了Fe-12Cr-2.5W-0.4Ti-0.3Y_2O_3合金,研究了压制压力及烧结温度对烧结体组织与性能的影响。结果表明:铬、钨原子在高能球磨过程中未能完全固溶于α-Fe中,而在烧结过程中能实现完全固溶;压坯密度和抗弯强度随压制压力增大而增加,并在压力达到700 MPa后趋于稳定;提高压制压力与烧结温度可提高烧结体抗拉强度,在压制压力700 MPa,烧结温度1400℃的条件下,烧结体抗拉强度为416.7 MPa,材料断裂方式为韧性断裂。 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.
出处 《机械工程材料》 CAS CSCD 北大核心 2011年第6期4-7,共4页 Materials For Mechanical Engineering
基金 国家自然科学基金重点资助项目(50634060)
关键词 粉末冶金 压制压力 烧结温度 抗拉强度 powder metallurgy pressing pressure sintering temperature tensile strength
  • 相关文献

参考文献10

  • 1UKAI 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.
  • 2UKAI 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.
  • 3UKAI S, FUJIWARA M. Perspective of ODS alloys applica- tion in nuclear enviorments[J]. Journal of Nuclear Materials, 2002,307/311(1) :749-751.
  • 4UKAI 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.
  • 5KIM I S, HUNN J D, HASHIMOTO N. Defect and void e- volution in oxide dispersion strengthened ferritic steels under 3. 2 MeV Fe^+ ion irradiation with simultaneous helium injec- tion[J]. Journal of Nuclear Materials,2000,280(3):264-274.
  • 6KIMURA A, SUGANO R, MATSUSHITA Y, et al. Ther- mal helium desorption behavior in advanced ferritic steels[J]. Journal of Physics and Chemistry of Solids, 2005, 66 (2/4): 504-508.
  • 7KLEUEH R L, HARRIES D R. High-chromium ferritic and martensitic steels for nuclear application [M]. American: ASTM International, 2001.
  • 8LEE 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.
  • 9OLIER 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,王荣辉.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. 被引量:1

二级参考文献11

  • 1曹玲飞,汪明朴,谢丹,郭明星,李周,谭望,徐根应.Thermal behavior and structure of Fe_(84)Nb_7B_9 nanocrystalline powders[J].中国有色金属学会会刊:英文版,2006,16(2):299-303. 被引量:1
  • 2Benjamin. Dispersion strengthened superalloys by mechanical alloying[J]. Metallurgical Transactions: A, 1970, 10(1): 2 943-2 951.
  • 3Weeb W, Barkker H. Amorphization by ball milling: a review[J]. Physical: B, 1988, 153(1-3):93-135.
  • 4Eekert J, Sehultz L, Urban K. Formation of quasicrystaline and amorphous phase in mechanical alloyed Al-based and Ti Ni based alloys[J]. Acta Metallurgica Materialia, 1991, 39(7): 1 497-1 506.
  • 5Yoshizawa Y, Oguma S, Yamauchi K. New Fe-based soft magnetic alloys composed of ultrafine grain structures[J]. Journal of Applied Physics, 1988, 64 (10):6 044-6 049.
  • 6Wang H, Ouyang L Z, Zeng M Q, et al. Direct Synthesis of MgCNi3 by mechanical alloying[J]. Scripta Materialia, 2004, 50(12): 1 471-1 474.
  • 7Ukai S, Harada M, Okada H, et al. Tube manufacturing and mechanical properties of oxide dispersion strengthened ferritic steel[J]. Journal of Nuclear Materials, 1993, 204(2):74-80.
  • 8Kimura 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): 50:1-508.
  • 9Ukai 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.
  • 10Kim I S, Hunn J D, Hashimoto N. Defect and void evolution in oxide dispersion strengthened ferritic steels under 3.2MeV Fe^+ ion irradiation with simultaneous helium injection[J]. Journal of Nuclear Materials, 2000, 280(3): 264-274.

同被引文献23

引证文献2

二级引证文献11

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部