Sliding Wear Behavior of Steam Generator Tube Materials in Nuclear Power Plants

Gyung Guk Kim; Ji Hui Kim; Kwon Yeong Lee; Seon Jin Kim; Deok Hyun Lee; Do Haeng Hur; Myung Sik Choi; Jung Ho Han

doi:10.4028/www.scientific.net/MSF.486-487.137

Paper Titles

Life Cycle Improvement Assessment of Al and Mg Diecasting Processes
p.121

Effects of the Duration of Potentiostatic Anodizing on the Corrosion Resistance and Surface Morphology of Films Formed on Mg-Al Alloys
p.125

Surface Morphology Characteristics and Improvements on Corrosion Resistance in Anodized Mg-Al Alloys as a Result of Sealing Treatments
p.129

Effects of Post-Weld Heat Treatment on Optimum Cathodic Protection Potential of High-Strength Steel in Marine Environment Conditions
p.133

Sliding Wear Behavior of Steam Generator Tube Materials in Nuclear Power Plants
p.137

Characterization of Long-Term Oxidized Nickel Aluminide Coating by Photoluminescence Spectroscopy
p.141

Characterization of Isothermally Oxidized ZrO₂-8wt.%Y₂O₃ Thermal Barrier Coatings by Electrochemical Impedance Spectroscopy
p.145

Transmission Electron Microscopy of Isothermally Oxidized EB-PVD Thermal Barrier Coating on (Ni,Pt)Al Bondcoat
p.149

Surface Characteristics of Ni-Diamond Composite Powders by Electroless Plating Method
p.153

HomeMaterials Science ForumMaterials Science Forum Vols. 486-487Sliding Wear Behavior of Steam Generator Tube...

Sliding Wear Behavior of Steam Generator Tube Materials in Nuclear Power Plants

Abstract:

Wear damage of steam generator tubes of nuclear power plants can cause leakage of radioactive substances. So the evaluation of tubes’ integrity is very important from the viewpoint of nuclear ecocide. In the present study, sliding wear behaviors of Inconel 600 and 690 steam generator tube materials mated with 409 stainless steel commonly used as the support plate were investigated at room temperature in an air environment. For more precise prediction of wear behaviors of steam generator tubes, Archard equation was modified, and the modified wear coefficients were estimated as a function of sliding distance. When using the modified Archard equation, the reliabilities for prediction of wear behavior of Inconel 600 and 690 mated with 409 stainless steel increased from 71.8% to 83.8% and from 60.2% to 85.2%, respectively.

You might also be interested in these eBooks

View Preview

Info:

Periodical:

Materials Science Forum (Volumes 486-487)

Pages:

137-140

DOI:

https://doi.org/10.4028/www.scientific.net/MSF.486-487.137

Citation:

Cite this paper

Online since:

June 2005

Authors:

Gyung Guk Kim, Ji Hui Kim, Kwon Yeong Lee, Seon Jin Kim, Deok Hyun Lee, Do Haeng Hur, Myung Sik Choi, Jung Ho Han

Keywords:

Modified Archard Equation, Silding Wear, Steam Generator Tubes

Export:

RIS, BibTeX

Price:

Permissions CCC:

Request Permissions

Permissions PLS:

Request Permissions

Сopyright:

Citation:

References

[1] P. J. Hofmann, T. Schettler and D. A. Steininger : ASME 86-PVP-2, (1986).

Google Scholar

[2] H. J. Connors : Nuclear Technology. Vol. 55, (1981) 311-331.

Google Scholar

[3] D. A. Rigney : Wear 175 (1994) 63-69.

Google Scholar

[4] J. Jiang, F. H. Stott, M. M. Stack : Wear 151 (1998) 245-256.

Google Scholar

[5] S. C. Lim, M. F. Ashby, J. H. Brunton : Acta metal. Vol. 35, (1987), 1343-1348.

Google Scholar

[6] E. Rabinowicz : Friction and Wear of Materials (Wiley, New York 1995) Archard equation Modified Archard equation Reliability K Reliability K(s) I600/S409 71. 8% 57. 1*10 -15 Pa -1 83. 8% 77. 2*10 -14 s 1. 69 I690/S409 60. 2% 48. 0*10 -15 Pa -1 85. 2% 70. 3*10 -14 s 1. 61.

Google Scholar