Stress Corrosion Cracking of Alloy 600 in a High-Temperature Water Containing Sulfate and Thiosulfate

Article Preview

Abstract:

The stress corrosion cracking (SCC) susceptibility of Alloy 600 MA has been studied in deaerated 0.01 M sodium sulfate (Na2SO4) and sodium thiosulfate (Na2S2O3) solutions at 340°C. Pre-strained reverse U-bend (RUB) specimens are tested using a static-autoclave system. The specimens show an intergranular SCC and a higher resistance to SCC in a Na2S2O3 solution than in a Na2SO4 solution. The results of the deposits and surface analyses by using XRD and SEM/EDS confirm the existence of the sulfides. The SCC of Alloy 600 MA is associated with the reduced sulfur species and protective oxide film properties formed on the alloy surface in the Na2SO4 and Na2S2O3 solutions.

You might also be interested in these eBooks

Info:

Periodical:

Key Engineering Materials (Volumes 277-279)

Pages:

644-648

Citation:

Online since:

January 2005

Export:

Price:

Permissions CCC:

Permissions PLS:

Сopyright:

© 2005 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

[1] A.K. Agrawal, W.N. Stiegelmeyer and W.E. Berry: EPRI NP-4504LD (EPRI, USA 1986).

Google Scholar

[2] L.E. Thomas, S.M. Bruemmer and P.M. Scott: Fontevraud 5 Int. Symp. (2003).

Google Scholar

[3] J.F. Newman: EPRI NP-3043 (EPRI, USA 1983).

Google Scholar

[4] T. Sakai, S. Okabayashi, K. Aoki, K. Matsumoto, F. Nakayasu and Y. Kishi: Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors (1989), pp.12-37.

Google Scholar

[5] O. Bouvier, M. Bouchacourt and P. Lemaire: Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors (2002).

Google Scholar

[6] O. Bouvier, B. Prieux, F. Vallant, M. Bouchacourt and P. Lemaire: Proc. 9 th Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors (1999), p.695.

DOI: 10.1002/9781118787618.ch72

Google Scholar

[7] N. Ogawa, T. Nakashiba, M. Yamada, R. Umebara, S. Okamoto and T. Tusruta: Proc. 8th Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors (1997), p.395.

Google Scholar

[8] B. Sala, P. Combrade, R. Erre, R. Benoit and M. Calvar: Proc. 5 th Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors (1991), p.502.

Google Scholar

[9] P. Combrade, M. Foucault, D. Vancon, P. marcus, J.M. Grimal and A. Gelpi: Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power System-Water Reactors (1989), pp.5-79.

Google Scholar

[10] P. Marcus and J.M. Grimal: Corrosion Science Vol. 31 (1990), p.377.

Google Scholar