Inconel 690（UNS N06690）

Inconel 690 special properties

Alloy 690 has excellent resistance to intergranular corrosion and intergranular stress corrosion cracking. It is mainly used as a material for heat transfer tubes of steam generators in pressurized water reactor nuclear power plants. The materials used in the steam generator heat transfer tubes of PWR nuclear power plants have undergone a course of development, including 304 austenitic stainless steel, 600 alloy, 800 alloy and 690 alloy. The study of corrosion failure in 600 alloy service shows that intergranular corrosion and intergranular stress corrosion cracking are the main problems. 690 alloy has been used as a material for the heat transfer tubes of steam generators in pressurized water reactor nuclear power plants. Since its use in the 1990s, no damage has been reported.

 

Inconel 690 chemical composition

Chemical composition (mass percentage) of nickel-based 690 alloy.

%	Ni	Cr	Fe	C	Mn	Si	Cu	P	S
Min.	margin	27	7
Max.		31	11	0.05	0.5	0.5	0.5	0.015	0.015

 

Inconel 690 physical properties

Density	Melting point	Yield strength	Tensile strength	Elongation	Hardness HRB
8.19g/cm	1343-1377℃	350MPa	700MPa	45%	85

 

Inconel 690 main application

690 alloy is mainly used for the material of the heat transfer tube of the steam generator of the PWR nuclear power plant. It is the core technology of the steam generator. At present, among the pressurized water reactor nuclear power plant units in operation in China, 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 pressurized water reactor nuclear power plants under construction and planning also use 690 alloy as the material of the steam generator heat transfer tube.

 

Can supply varieties and specifications: forgings, bars, sheets, strips, rings, wire, bolts, springs, etc. Negotiable supply, can be produced according to customer requirements.