Ten Years Experience on Inconel Alloys Since the Bugey Leak in 1991

Author(s):  
Franc¸ois Champigny ◽  
Claude Pages ◽  
Claude Amzallag ◽  
Franc¸ois Billy

Base nickel alloys like Inconel 600 or 182 are particularly sensitive to stress corrosion cracking. This fact is well known since Corriou’works at the beginning of the sixties and its applications to the steam generator tubes in the seventies. For the RP vessel heads, the major fact of the nineties was the leak that occurred on one penetration in 1991 in the French NPP unit of Bugey. Several important decisions were taken after discover of this leak. First of them was to understand why it appeared so quickly, then test repairs for the Bugey case, then decide to replace all vessel heads considering that the repair solutions was to high cost. In parallel many developments were launched to establish laws for PWSCC and develop non-destructive methods to inspect the head penetrations. The conclusions obtained show the decision was good and no new leak happened on the VH penetrations.

Author(s):  
Deok Hyun Lee ◽  
Do Haeng Hur ◽  
Myung Sik Choi ◽  
Kyung Mo Kim ◽  
Jung Ho Han ◽  
...  

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].


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 ◽  
...  

CORROSION ◽  
1978 ◽  
Vol 34 (11) ◽  
pp. 369-378 ◽  
Author(s):  
R. S. PATHANIA ◽  
J. A. CHITTY

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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