Characterization of damage and triboparticles resulting from fretting of Incoloy 800 steam generator tubes against different materials

Wear ◽  
2017 ◽  
Vol 390-391 ◽  
pp. 198-208 ◽  
Author(s):  
S.R. Soria ◽  
A. Tolley ◽  
A. Yawny
1995 ◽  
Vol 8 (3) ◽  
pp. 309-318 ◽  
Author(s):  
B. Benoist ◽  
P. Gaillard ◽  
M. Pigeon ◽  
P. Morizet-Mahoudeaux

Author(s):  
Sandra Pagan ◽  
Xinjian Duan ◽  
Michael J. Kozluk ◽  
Brian Mills ◽  
Guylaine Goszczynski

Canadian nuclear standard CSA N285.4 requires the periodic metallurgical examination of removed ex-service steam generator tubes. This paper describes the practices used for the characterization and structural integrity tests of ex-service steam generator tubes at Ontario Power Generation (OPG). It shows that there is no degradation in mechanical properties of Monel 400 tubes after 7 to 18 Effective Full Power Years (EFPY) of operation and Incoloy 800 tubes after more than 10 EFPY of operation.


2008 ◽  
Vol 59 (9) ◽  
Author(s):  
Dumitra Lucan ◽  
Manuela Fulger ◽  
Gheorghita Jinescu

The Steam Generators (SG), equipment that ensures the connection between the primary and secondary circuits, creates several safety problems during operation, mainly due to corrosion and mechanical damages. To provide information about the corrosion behaviour of the structural materials from CANDU SG under normal and abnormal conditions of operation and to identify the failure types produced by the corrosion were performed corrosion experiments consisting in chemical accelerated tests, static autoclaving and electrochemical methods. The gravimetric method, optical metallographic microscopy, XRD and EDS analysis, as well as electrochemical measurements have been used to evaluate the corrosion behavior of the steam generator tubes material (Incoloy-800).


Author(s):  
Mitch Hokazono ◽  
Clayton T. Smith

Integral light-water reactor designs propose the use of steam generators located within the reactor vessel. Steam generator tubes in these designs must withstand external pressure loadings to prevent buckling, which is affected by material strength, fabrication techniques, chemical environment and tube geometry. Experience with fired tube boilers has shown that buckling in boiler tubes is greatly alleviated by controlling ovality in bends when the tubes are fabricated. Light water reactor steam generator pressures will not cause a buckling problem in steam generators with reasonable fabrication limits on tube ovality and wall thinning. Utilizing existing Code rules, there is a significant design margin, even for the maximum differential pressure case. With reasonable bend design and fabrication limits the helical steam generator thermodynamic advantages can be realized without a buckling concern. This paper describes a theoretical methodology for determining allowable external pressure for steam generator tubes subject to tube ovality based on ASME Section III Code Case N-759-2 rules. A parametric study of the results of this methodology applied to an elliptical cross section with varying wall thicknesses, tube diameters, and ovality values is also presented.


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