Testing Steam Generator Materials For Pressurized Water Reactor Plants

Journal Article · Mon Jan 01 04:00:00 EST 1962 · Corrosion (Houston)

DOI:https://doi.org/10.5006/0010-9312-18.1.27· OSTI ID:4802283

McGREW, J. O. H. N. W.

Selected materials for use in nuclear power plant steam generators were evaluated in a simulated nuclear system. Low carbon steel, Croloy 16-1, and Inconel were compared to AISI Type 304 in their resistance to general corrosion, pitting, and stress corrosion cracking, The secondary environments were unusually severe, so that differences among the metals tested would be apparent within a reasonable test time. Simultaneously, overall performance would serve to indicate the difficulties that might be encountered in attempting to operate a field reactor with little or no treatment of the secondary water. The AISI Type 304 superheater cracked severely from chloride stress corrosion and the test was discontinued after 1927 hours. A bimetal steam generator and superheater with the AISI 1020 carbon steel side of the tubes in contact with the secondary environment were service tested 5041 hours without failure. A steam generator and superheater with Croloy 16-1 tubes and a steam generator and superheater with Inconel tubes were service tested 4253 and 3819 hours respectively without failure. The Inconel vessels were superior to all of the others in the test environments used.

• Research Organization: Martin Co., Baltimore
• Sponsoring Organization: USDOE
• NSA Number: NSA-16-007856
• OSTI ID: 4802283
• Journal Information: Corrosion (Houston), Journal Name: Corrosion (Houston) Journal Issue: 1 Vol. 18; ISSN 0010-9312
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

36 MATERIALS SCIENCE
CARBON STEELS
CHLORIDES
CHROMIUM ALLOYS
CORROSION
CRACKS
GENERATORS
HIGH TEMPERATURE
MATERIALS TESTING
NICKEL ALLOYS
STAINLESS STEELS
STEAM
STRESSES
VESSELS
WATER