SCC of cold-worked austenitic stainless steels in PWR conditions

• Autorzy: Raquet O. , Herms E. , Vaillant F. , Couvant T.
• Języki publikacji: EN

Abstrakty

EN

A strong susceptibility for SCC of heavily cold worked austenitic stainless steels is observed in hydrogenated primary water typical of PWRs. This susceptibility to cracking increases with the extent of cold-work and/or localization of deformation. The levels of cold-work involved in this study are very high when compared to the maximum cold-work levels required by the usual international codes relevant to PWRs (ASME and RCC-M). These high values of cold-work could be eventually encountered on the surface of same components (grinding) or in the case of improper manufacturing. The specific cold-work procedures including a compressive stage (fatigue, shot-peening) strongly favors SCC susceptibility in PWRs conditions under dynamic deformation. For a given cold-working procedure, SCC susceptibility of austenitic stainless steels materials increases with an increasing intensity of cold-work. A threshold of SCC susceptibility was identified in the ease of the shot-peening procedure of cold-working for AISI 304L stainless steels through the value of the initial surface hardness before SCC testing (CERT). SCC crack propagation is thus only observed beyond 300+-10HV on shot-peened specimens.

Słowa kluczowe

EN

stress corrosion cracking; cold work; austenitic stainless steels; hydrogen embrittlement; primary water

• Wydawca: Politechnika Gdańska
• Czasopismo: Advances in Materials Science
• Rocznik: 2007
• Tom: Vol. 7, nr 1(11)
• Strony: 33--46
• Opis fizyczny: Bibliogr. 20 poz., rys., tab.

Twórcy

autor

Raquet O.

autor

Herms E.

autor

Vaillant F.

autor

Couvant T.

• Commissaria l'Energie Atomique (CEA), DEN/DPC/SCCME/LECA, 91191 Gif-sur-Yvette Cedex, France

Bibliografia

• [1] B.M. Gordon, "The effect of chloride and oxygen on the stress corrosion of stainless steels: review of literature", Materials Performance, 19 (4) 1980.
• [2] B.M. Gordon, "Corrosion in Boiling Water Reactors", ASM Metals Handbook vol. 13 Corrosion, (Metal Park, Ohio: ASM International, 1987).
• [3] M.O. Speidel, Corrosion of stainless steels (A.J. Sedricks, Wiley-Interscience publication) 1979.
• [4] M.O. Speidel, R. Magdowski, 9th International Symposium on Environmental of Materials in Nuclear rower Systems - Water Reactors (Edited by F.P. Ford, S.M. Bruemmer and G. Was, TMS, 1999),325.
• [5] J. Kuniya, I. Masaoka, R. Sasaki, Corrosion 44 (1) (1988), pp. 21-28.
• [6] H. Hanninen, "Effect of sensitization and cold work on stress corrosion susceptibility of austenitic stainless steels in BWR and PWR conditions" (VTT Metals Laboratory Report 88, May 1981).
• [7] M. Tsuboda, Y. Kanazawa, I. Hitoshi, 7th International Symposium on Environmental of Materials in Nuclear rower Systems - Water Reactors, August 7-10, 1995, Breckenridge, Colorado.
• [8] P. Andresen, T.M. Angeliu, W.R. Catlin, LM. Young, R.M. Horn, Corrosion 2000 conference, paper 203 (NACE International publications).
• [9] P. Andresen, T.M. Angeliu, LM. Young, Corrosion 2001 conference, paper 228 (NACE International publications).
• [10] Z. Szklarska-Smialowska, S.W. Sharkawy, Z. Xia, Journal of Nuclear Materials 195 (1992), pp. 184-190.
• [11] Z. Szklarska-Smialowska, S.W. Sharkawy, Z. Xia, Corrosion 48 (6) (1992), pp. 455-462.
• [12] T. Couvant, P. Moulart, L Legras, P. Bordes, J. Capelle, Y. Rouillon, T. Balon, Colloque International Fontevraud 6, Fońtevraud, France, septembre 2006 (SFEN Publications).
• [13] E.P. Simonen, S.M. Bruemmer, Corrosion 97 conference, paper 106 (NACE International publications ).
• [14] K. Arioka, Y. Kaneshima, T. Yamada, T. Terachi, 11th International Symposium on Environmental of Materials in Nucklear rower Systems - Water Reactors, Stevenson, W A, USA, 10-14 August 2003.
• [15] K. Arioka, Colloque International Fontevraud 5, Fontevraud, France, septembre 2002 (SFEN Publications).
• [16] M.L. Castafio, M.S. Garcia, G. de Diego, D. Gomez-Briceno, L. Francia, Colloque International Fontevraud 5, Fontevraud, France, septembre 2002 (SFEN Publications).
• [17] M.L. Castano, M.S. Garcia Redondo, G. de Diego Velasco, D. Gomez Briceno, 11th International Conference Environmental Degradation of Materials in Nuclear Systems - Water Reactors, Stevenson, W A, USA, 10-14 August 2003.
• [18] T. Shoji, G. Li, J. Kwon, S. Matshushima, Z. Lu, 11th International Symposium on Environmental of Materials in Nuclear Power Systems - Water Reactors, Stevenson, WA, USA, 10-14 August 2003.
• [19] S. Usami, T. Mori, Cryogenics, 40 (2) (2000), pp. 117-126.
• [20] F. Vaillant, T. Couvant, J.M. Boursier, C. Arnzallag, Y. Rouillon, O. Raquet, 2004 Pressure Vessels and Piping Conference, San Diego, USA, 25-29 july 2004.