Intergranular attack and stress corrosion cracking propagation behavior of alloy 600 in high-temperature caustic solution

Corrosion

Volumn 55, Issue 6, 1999, Pages 566-575

  Kawamura, H ^a   Hirano, H ^a  

^a CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY   (Japan)

Author keywords

Alloy 600; Crack growth rate; Double cantilever beam; High temperature water; Intergranular attack; Oxide film; Statically indeterminate model; Stress corrosion cracking; Stress intensity factor

Indexed keywords

EID: 0346395783     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3280497     Document Type: Article

References (2)

1. A. Kishida, H. Takamatsu, H. Kitamura. S. Isobe, K. Omimura, K. Arioka, T. Hattori, T. Arai, M. Sato, "Causes and Remedial Measures of Steam Generator Tube Intergranular Attack in Japanese PWR," Proc. 3rd Int. Symp. Environmental Degradation of Materials In Nuclear Power Systems - Water Reactors (Warrendale, PA: The Metallurgical Society, 1987), p. 465.
2. R.E. Hermer, J.B. Prestegiacomo, C.R. Wolfe, "Causes and Remedies of Alloy 600 IGA/SCC," EPRI/SG Owners Group Project S302-13, Subtask 210 Background Report, Westlnghouse Corp. Atomic Power Division Report No. 10523 (1984).