Predicting susceptibility to intergranular stress corrosion cracking of alloy 690

Corrosion

Volumn 56, Issue 11, 2000, Pages 1133-1139

  Casales, M ^a  

^a UNIVERSIDAD AUTÓNOMA DEL ESTADO DE MORELOS   (Mexico)

Author keywords

Alloy 690; Chromium depletion; Intergranular attack; Sensitization; Stress corrosion cracking

Indexed keywords

EID: 2342645245     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3294398     Document Type: Article

References (2)

1. M.A. Cordobi, "Corrosion Resistance of Alloy 690 In PWR Steam Generator Environments," Proc. Workshop on Thermally Treated Alloy 690 tubes for Nuclear Steam Generators, EPRI NP-46655-SR (Palo Alto CA: Electric Power Research Institute, 1986), p. 8-1 to 8-15.
2. K. Norring, K. Stiller, J.O. Nillson, 5th Int. Symp. on Environmental Degradation of Materials for Nuclear Power Systems-Water Reactors (Houston, TX: NACE International, 1991), p. 855.