Effects of Pb on SCC of Alloy 600 and Alloy 690 in prototypical steam generator chemistries

Materials Science Forum

Volumn 475-479, Issue II, 2005, Pages 1387-1392

  Lumsden, Jesse ^a   Mcllree, Allan ^b   Eaker, Richard ^c   Thompson, Rocky ^d   Slosnerick, Steve ^e  

^a ROCKWELL SCIENTIFIC COMPANY   (United States)

^b ELECTRIC POWER RESEARCH INSTITUTE   (United States)

^c DUKE ENERGY   (United States)

^d Florida Power Corporation   (United States)

^e First Energy   (United States)

Author keywords

Alloy 600; Alloy 690; Corrosion potential; Intergranular corrosion; Lead cracking; Once through steam generators; Steam generators; Stress corrosion cracking

Indexed keywords

ALLOYS; ALUMINUM COMPOUNDS; HEAT TREATMENT; LEAD; NITRIC ACID; PH; STRESS CORROSION CRACKING; TRANSMISSION ELECTRON MICROSCOPY;

ALLOY 600; ALLOY 690; INTERGRANULAR CORROSION; LEAD CRACKING; ONCE THROUGH STEAM GENERATORS;

STEAM GENERATORS;

EID: 17044378531     PISSN: 02555476     EISSN: 16629752     Source Type: Book Series    
DOI: 10.4028/0-87849-960-1.1387     Document Type: Conference Paper

References (2)

1. R. W. Staehle: Assessment of and Proposal for a Mechanistic Interpretation of the SCC of High Nickel Alloys in Lead-Containing Environments, 11th Environ. Degrad. ANS, 2003, p.381.
2. D. P. Rochester and R. W. Eaker: Laboratory Examination Results from Oconee Nuclear Station Once through Steam Generator Tubes, 9th Environ. Degrad., TMS, 2000, p.639.