ANPP CORROSION PROGRAM. Final Summary Report

Technical Report · Thu Feb 01 04:00:00 EST 1962

OSTI ID:4802714

Mayes, I C; McGrew, J

Results are presented of a program to investigate the suitability of various materials for heat exchanger fabri-cation in nuclear power plants and to investigate the effects of various water treatments on the performance of these materials. Static autoclave and dynamic loop tests were performed. Results of tests showed that Inconel is superior to all other materials tested in simulated nuclear service. A wide range of environments from high purity water to water containing high chloride concentrations was used. The criteria of comparison included resistance to general corrosion, pitting corrosion, crevice corrosion, and susceptibility to stress corrosion cracking. AISl Type 304 austenitic stainless steel, AlSI Type 430 ferritic stainless steel, Inconel, Monel and Ni were tested in tilting autoclaves. Test exposures varied considerably, as did environmental composition. The Type 304 stainless steel cracked severely in 120- hour tests. The Type 430 stainless steel pitted badly in 120-hour tests. Inconel suffered very slight incipient attack after 2000 hours' exposure to a severe environment. Both Monel and nickel pitted somewhat after 2000 hours' exposure to a severe environment. (auth)

• Research Organization: Martin Co. Nuclear Div., Baltimore
• NSA Number: NSA-16-013532
• OSTI ID: 4802714
• Report Number(s): MND-E-2727
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

AUSTENITE
AUTOCLAVES
CHLORIDES
COPPER ALLOYS
CORROSION
CRACKS
HEAT EXCHANGERS
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
NICKEL
NICKEL ALLOYS
PRESSURE VESSELS
STAINLESS STEELS
WATER