Product Features

690 alloy 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 for heat transfer tubes in steam generators of pressurized water reactor nuclear power plants have undergone a development process, including 304 austenitic stainless steel, 600 alloy, 800 alloy, and 690 alloy. The study on corrosion failure of 600 alloy in service shows that intergranular corrosion and intergranular stress corrosion cracking are the main problems. There have been no reports of damage to 690 alloy as a heat transfer tube material for steam generators in pressurized water reactor nuclear power plants since it was put into use in the 1990s.

Application scope and field

690 alloy is mainly used as a heat transfer tube material for steam generators in pressurized water reactor nuclear power plants. The core technology of steam generator. At present, among the pressurized water reactor nuclear power plant units already in operation in China, only Qinshan Phase I uses 800 alloy. Qinshan Phase II, Daya Bay, and Ling'ao nuclear power plants all use 690 alloy as the heat transfer tube material for steam generators. Most of the pressurized water reactor nuclear power plants under construction and planning also use 690 alloy as the heat transfer tube material for steam generators.