INCONEL 690 ( UNS N06690 )
Chemical composition of nickel base alloy 690
Ni |
Cr |
Fe |
C |
Al |
Ti |
Mn |
Si |
Cu |
P |
S |
Bal. |
30.39 |
8.88 |
0.023 |
0.22 |
0.26 |
0.23 |
0.07 |
0.02 |
0.006 |
0.002 |
The physical and mechanical properties of annealed 690 alloy.
Density |
Melting |
Young's modulus |
Poisson's ratio |
Yield strength |
Tensile strength |
Elongation |
8.19g/cm |
1343-1377ºC |
211GPa |
0.289 |
350MPa |
700MPa |
45% |
Special performance
Alloy 690 has excellent resistance to intergranular corrosion and intergranular stress corrosion cracking, and is mainly used as a heat transfer tube material for steam generators in pressurized water reactor nuclear power plants. The materials used for the heat transfer tube of the steam generator of the PWR nuclear power plant have gone through a development process, including 304 austenitic stainless steel, 600 alloy, 800 alloy and 690 alloy. Research on corrosion failure of 600 alloy in service shows that intergranular corrosion and intergranular stress corrosion cracking are the main problems. Alloy 690 is used as the heat transfer tube material for the steam generator of the PWR nuclear power plant. Since it was put into use in the 1990s, no damage has been reported.
Main application
Alloy 690 is mainly used for the heat transfer tube material of the steam generator of the PWR nuclear power plant, and is the core technology of the steam generator. At present, among the PWR nuclear power plants in operation in my country, only Qinshan Phase I uses 800 alloy, and Qinshan Phase II, Daya Bay and Ling Ao nuclear power plants all use 690 alloy as the steam generator heat transfer tube material. Most of the PWR nuclear power plants under construction and planning also use alloy 690 as the steam generator heat transfer tube material. However, the 690 alloy tubes used in PWR nuclear power plants that have been in operation in China are basically purchased from abroad.