In order to qualify Inconel for service in the steam generation system of pressurized water nuclear power plants, the behavior of this material was investigated with respect to resistance to corrosion, radioactivity of corrosion products, and fabrication. The present paper presents the corrosion data. Corrosion tests were conducted in simulated primary and secondary reactor waters on Inconel specimens in several conditions of heat treatment and composition. Stressed specimens, weldments, galvanic couples, and crevice specimens were included. Under all conditions a tightly adherent film formed on the specimens and the corrosion rates were comparable to those of austenitic stainless steels. The Inconel alloy does not suffer intergranular attack or stress corrosion cracking in reactor waters. 6.3.10

Subject
Primary water, Water, Materials, Stainless alloys, Corrosion rate, Nickel based alloys, Autoclaves, Corrosion loops, Corrosion products, Crevices, Weight loss, Stainless steel, Heat treatment
© 1960 National Association of Corrosion Engineers
1960
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