论文信息 - Corrosion behavior of Alloy 690 and Alloy 693 in simulated nuclear high level waste medium - 字舞流文

Corrosion behavior of Alloy 690 and Alloy 693 in simulated nuclear high level waste medium

B. Raj | U. K. Mudali | Girija Suresh | P. K. Samantaroy | R. Paul

[1] Weite Wu,et al. Cavitation erosion behavior of Inconel 690 alloy , 2008 .

[2] J. Mayer,et al. Effects of Nb on the microstructure and corrosive property in the Alloy 690–SUS 304L weldment , 2005 .

[3] D. Agarwal,et al. Nickel and Nickel Alloys , 2004 .

[4] R. Dayal,et al. Corrosion assessment of type 304L stainless steel in nitric acid , 2003 .

[5] R. Dayal,et al. Microstructure and pitting corrosion aspects of as-weld and thermally aged 316 stainless steel SMA weld deposits containing different nitrogen contents , 2002 .

[6] Leopold Vehovar,et al. Stainless steel containers for the storage of low and medium level radioactive waste , 2001 .

[7] G. Santarini,et al. Mechanism of corrosion of AISI 304L stainless steel in the presence of nitric acid condensates , 2000 .

[8] K. Stiller,et al. Microstructure of a boron containing high purity nickel-based alloy 690 , 2000 .

[9] M. Joe,et al. Characterisation of sensitisation of type 409 stainless steel , 1999 .

[10] Joung-Soo Kim,et al. Investigation of IGSCC behavior of sensitized and laser-surface-melted Alloy 600 , 1998 .

[11] J. Kai,et al. The IGSCC, sensitization, and microstructure study of Alloys 600 and 690☆ , 1993 .