通过考察不同氢含量GH690合金的断裂韧性,探讨了氢对该合金断裂韧性和断裂行为的影响规律.结果表明,随着氢含量的提高,合金的断裂韧性逐渐降低,断口形貌由穿晶断裂转变为沿晶断裂.研究发现氢富集于晶界碳化物与基体界面处形成的空洞是导致合金断裂韧性降低的主要原因,且合金的氢含量越高,空洞增大的趋势越明显,从而导致合金抵抗裂纹扩展的能力越差,故断裂韧性越低.
参考文献
[1] | Stiller K,Nilsson J O,Norring K.Structure,chemistry,and stress corrosion cracking of grain boundaries in alloys 600 and 690[J].Metall.Mater.Trans.,1996,27A (2):327. |
[2] | Sui G,Titchmarsh J M,Heys G B,et al.Stress corrosion cracking of alloy 600 and alloy 690 in hydrogen/steam at 380 ℃[J].Corros.Sci.,1997,39(3):565. |
[3] | Kai J J,Yu G P,Tsai C H,et al.Effects of heat treatment on the chromium depletion,precipitate evolution,and corrosion resistance of INCONEL alloy 690[J].Metall.Mater.Trans.,1989,20A(10):2057. |
[4] | Diercks D R,Shack W J,Muscara J.Overview of steam generator tube degradation and integrity issues[J].Nucl.Eng.Design,1999,194(1):19. |
[5] | Symons D M.Effect of carbide precipitation on the hydrogen-enhanced fracture behavior of alloy 690[J].Metall.Mater.Trans.,1998,29A(4):1265. |
[6] | 邹岷.800H和690合金的氢渗透及氢脆研究前瞻[J].核动力工程,2003,24(1):37. |
[7] | Yong B A,Gao X S,Srivatsan T S.The response of alloy 690 tubing in a pressurized water reactor environment[J].Mater.Design,2007,28(10):373. |
[8] | Brown C M,Mills W J.Fracture toughness of alloy 690 and EN52 welds in air and water[J].Metall.Mater.Trans.,2002,33A(6):1725. |
[9] | Mills W J.On the relationship between stretch zone formation and the J integral for high strain-hardening materials[J].J.Testing Eval.,1981,9(1):56. |
[10] | 褚武扬.氢损伤与滞后断裂[M].北京:冶金工业出版社,1988.190 |
[11] | 褚武扬,乔立杰,陈奇志.断裂与环境断裂[M].北京:科学出版社,2000.101. |
[12] | 李秀艳,李依依.奥氏体合金的氢损伤[M].北京:科学出版社,2003.13. |
[13] | Liang Y,Sofronis P.On hydrogen-induced void nucleation and grain boundary decohesion in nickel-base alloys[J].Trans.ASME,2004,126(4):368. |
[14] | 王富强,王磊,刘杨.GH690合金的氢致脆性行为研究[J].郑州大学学报,2009,30(1):34. |
[15] | 朱继洲.压水堆核电厂的运行[M].北京:原子能出版社,2000.237. |
上一张
下一张
上一张
下一张
计量
- 下载量()
- 访问量()
文章评分
- 您的评分:
-
10%
-
20%
-
30%
-
40%
-
50%