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Corrosion testing of INCONEL alloy 690 for PWR steam generators

Journal Article · · J. Mater. Energy Syst.; (United States)
DOI:https://doi.org/10.1007/BF02833403· OSTI ID:5934447
INCONEL alloy 690, an austenitic, high-chromium modification of INCONEL alloy 600, was developed to resist stress-corrosion cracking and general corrosion in hightemperature aqueous environments associated with nuclear steam generators. Tests in nitric acid and nitric-hydrofluoric acid show that the high chromium content provides alloy 690 with good resistance to highly oxidizing environments over a wide range of high temperatures and oxygen concentrations, in the presence of crevices and lead or chloride contamination. Alloy 690 releases a negligible amount of material when exposed to high-velocity water at elevated temperatures. In constant extension rate tests, alloy 690 resists crack propagation in a deaerated 10 pct solution of sodium hydroxide better than alloy 600. Long-time tests also suggest greater resistance to intergranular attack in deaerated caustic solutions and to the oxidation of radioactive waste disposal involving nitric-hydrofluoric acid dissolution and vitrification.
Research Organization:
Huntington Alloys, Inc., Huntington, WV 25720
OSTI ID:
5934447
Journal Information:
J. Mater. Energy Syst.; (United States), Journal Name: J. Mater. Energy Syst.; (United States) Vol. 4:3; ISSN JMSMD
Country of Publication:
United States
Language:
English