压制压力及烧结温度对Fe-Cr-W-Ti-Y2O3合金组织与性能的影响
Effects of Pressing Pressure and Sintering Temperature on the Microstructure and Properties of Fe-Cr-W-Ti-Y2O3 Alloy
摘 要
采用粉末冶金法制备了Fe-12Cr-2.5W-0.4Ti-0.3Y2O3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1 400 ℃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。
压制压力
烧结温度
抗拉强度
powder metallurgy
pressing pressure
sintering temperature
tensile strength
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.
中图分类号 TF125
所属栏目
基金项目 国家自然科学基金重点资助项目(50634060)
收稿日期 2010/6/5
修改稿日期 2011/3/26
网络出版日期
作者单位点击查看
备注姚振华(1984-), 男, 湖北武汉人, 博士研究生。
引用该论文: 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 for mechancial engineering, 2011, 35(6): 4～7
姚振华,熊惟皓,彭倩筠,周敏. 压制压力及烧结温度对Fe-Cr-W-Ti-Y2O3合金组织与性能的影响[J]. 机械工程材料, 2011, 35(6): 4～7
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参考文献
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【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.
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