期刊文献+

国产新型锆合金SZA-4、SZA-6管材氢化物应力再取向研究 被引量:2

Study on Hydride Stress Reorientation of Domestic New Type Zircalloy SZA-4 and SZA-6 Tubing
下载PDF
导出
摘要 采用氢氩气相渗氢法、慢速率拉伸实验机进行氢化物应力取向及再取向实验,利用金相显微镜和Mias图像处理系统等方法,研究了环向应力和热循环次数对SZA-4和SZA-6两种国产新型锆合金管材氢化物应力再取向的影响。结果表明,SZA-4管材和SZA-6管材的应力取向因子(F_N(40°))随着应力和热循环次数的增加而增大,然后逐渐趋于N稳定,且SZA-6管材比SZA-4管材更易发生氢化物应力再取向0。对于SZA-4管材,F_N(40°)不大于0.45;SZA-6管材,F_N(40°)不大于0.7。 The effects of loop stress and thermal cycling times on the hydride stress reorientation behavior of two kinds of domestic zircalloy SZA-4 and zircalloy SZA-6 tubing were studied by carrying out hydride stress orientation and reorientation test with hydrogen argon gas permeability method and slow rate tensile testing machine and using metallographic microscope and Mias image processing system.The results show that the stress orientation factor(F_N(40°))of SZA-4 and SZA-6 tubing Nincreases with the increase of the stress and the numbers of thermal cycling times,and then tends to become stable.The hydride stress reorientation is easier to occur in SZA-6 tubing than that in SZA-4 tubing.For SZA-4 tubing,the obtained F_N(40°)is less than 0.45,and for SZA-6 tubing,the obtained F_N(40°)is less than 0.7.
作者 高雯 杨忠波 陈勇 袁改焕 杨帆 GAO Wen;YANG Zhongbo;CHEN Yong;YUAN Gaihuan;YANG Fan(Nuclear Power Institute of China,Chengdu 610213,China;State Nuclear Bao Ti Zirconium Industry Company,Baoji 721013,China;Chengdu Rail Transit Company,Chengdu 610210,China)
出处 《热加工工艺》 北大核心 2019年第2期71-75,共5页 Hot Working Technology
基金 国家自然科学基金资助项目(11775206)
关键词 SZA-6锆合金 SZA-4锆合金 氢化物 取向因子 zircalloy SZA-6 zircalloy SZA-4 hydride orientation factor
  • 相关文献

参考文献1

二级参考文献29

  • 1王卫国,周邦新.锆合金板织构的控制[J].核动力工程,1994,15(2):158-163. 被引量:19
  • 2王卫国,周邦新.轧制温度对Zr-4合金板织构的影响[J].核动力工程,1996,17(3):255-261. 被引量:7
  • 3Cox B.Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding-A review[J].Journal of Nuclear Materials,1990,172:249.
  • 4弗罗斯特BRT 周邦新译.核材料(第II部分)[M].北京:科学出版社,1999..
  • 5Tenckhoff E.Deformation Mechanisms,Texture,and Anisotropy in Zirconium and Zircaloy[R].ASTM-STP 966,1988.
  • 6Pochettino A A,Gannio N,Edwards C,et al.Texture and pyramidal slip in Ti,Zr and their alloys[J].Scripta Metallurgica et Materialia,1992,27:1859.
  • 7Rapperport E J,Hartley C S.Deformation Modes of Zirconium at 77,300,575 and 1075 K[R].NMI-1221,Nuclear Metals,Inc.,Concord,MA,1959.
  • 8Chun Y B,Hwang S K,Kim M H.Effect of Mo addition on the crystal texture and deformation twin formation in Zr-based alloys[J].Journal of Nuclear Materials,2001,295:31.
  • 9Francillette H,Bacroix B,Gasperini M.Effect of initial texture on deformation mechanisms and texture evolutions of Zr α polycrystals deformed by channel-die compression tests[J].Materials Science and Engineering A,1997,234-236:974.
  • 10Salinas Rodriguez A.Grain size effects on the texture evolution of α-Zr[J].Acta Metall.Mater.,1995,43(2):485.

共引文献53

同被引文献26

引证文献2

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