Effect of Composition and Heat Treatment on Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes in Sodium Hydroxide

CORROSION ◽  
1982 ◽  
Vol 38 (1) ◽  
pp. 40-45 ◽  
Author(s):  
J. R. Crum
Keyword(s):  
Heat Treatment ◽  
Stress Corrosion ◽  
Sodium Hydroxide ◽  
Steam Generator ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Alloy 600 ◽  
Steam Generator Tubes

The Geometry of Steam Generator Tube and Its Relevance to the Occurrence of Stress Corrosion Cracking in Operating Nuclear Power Plants

2010 ◽  
Author(s):  
Deok Hyun Lee ◽  
Do Haeng Hur ◽  
Myung Sik Choi ◽  
Kyung Mo Kim ◽  
Jung Ho Han ◽  
...  
Keyword(s):  
Stress Corrosion ◽  
Steam Generator ◽  
Stress Corrosion Cracking ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Corrosion Cracking ◽  
Location Type ◽  
Steam Generator Tubes ◽  
Non Destructive

Occurrences of a stress corrosion cracking in the steam generator tubes of operating nuclear power plants are closely related to the residual stress existing in the local region of a geometric change, that is, expansion transition, u-bend, ding, dent, bulge, etc. Therefore, information on the location, type and quantitative size of a geometric anomaly existing in a tube is a prerequisite to the activity of a non destructive inspection for an alert detection of an earlier crack and the prediction of a further crack evolution [1].

Relationship Between Acid Intergranular Corrosion and Caustic Stress Corrosion Cracking of Alloy 600

CORROSION ◽  
1977 ◽  
Vol 33 (1) ◽  
pp. 20-26 ◽  
Author(s):  
G. J. THEUS
Keyword(s):  
Heat Treatment ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Alloy 600 ◽  
Intergranular Attack ◽  
Electrochemical Tests ◽  
Stress Relieving ◽  
Service Conditions ◽  
The Relationship

Abstract Modified Streicher and 288 C (550 F) electrochemical caustic stress corrosion tests were performed on Alloy 600 to determine the relationship between acid intergranular attack susceptibility and caustic stress corrosion cracking (SCC) susceptibility. Mill annealed and solution annealed materials with and without a subsequent 621 C (1150 F) heat treatment (simulated stress relief) were evaluated. Susceptibility to attack in the Streicher test was greatest for material that had received a 621 C (1150 F) heat treatment, whereas this heat treatment caused the same material to be least susceptible to cracking in the electrochemical tests. The conclusions drawn from these results are: (1) stress relieving Alloy 600 does improve its resistance to caustic SCC, and (2) resistance of Alloy 600 to acid intergranular attack does not imply resistance of Alloy 600 to caustic SCC. Therefore, the results demonstrate the need for selecting corrosion qualification tests which are relevant to service conditions.

Assessment of primary water stress corrosion cracking of PWR steam generator tubes

1992 ◽  
Vol 134 (2-3) ◽  
pp. 199-215 ◽  
Author(s):  
V.N. Shah ◽  
D.B. Lowenstein ◽  
A.P.L. Turner ◽  
S.R. Ward ◽  
J.A. Gorman ◽  
...  
Keyword(s):  
Water Stress ◽  
Stress Corrosion ◽  
Steam Generator ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Primary Water ◽  
Steam Generator Tubes

Stress Corrosion Cracking of Steam Generator Tube Materials in Sodium Hydroxide Solutions

CORROSION ◽  
1978 ◽  
Vol 34 (11) ◽  
pp. 369-378 ◽  
Author(s):  
R. S. PATHANIA ◽  
J. A. CHITTY
Keyword(s):  
Stress Corrosion ◽  
Sodium Hydroxide ◽  
Applied Stress ◽  
Steam Generator ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Sodium Hydroxide Concentration ◽  
Inconel 600 ◽  
Steam Generator Tubing ◽  
Monel 400

Abstract Stress corrosion cracking (SCC) tests were carried out on specimens of Monel 400, Inconel 600, and Sanicro 30 steam generator tubing in solutions containing 10 to 500 g NaOH/kg H2O at 300 C for times up to 600 days. Applied stress and sodium hydroxide concentration had a significant effect on the (SCC) resistance of the three materials.

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