Abstract
Even if Alloy 182 is usually exhibiting a high susceptibility to cracking in the laboratory, the field experience did not reveal to date a significant susceptibility to PWSCC in PWRs, when the welds have been perfectly stress relieved. However, recently, an increasing number of cracks was reported in USA, Sweden and Japan on Alloy 182 and a few cases on Alloy 82. This paper addresses the work on initiation of PWSCC engaged at EDF R&D (MAI). The main objective is to calibrate an engineering model to predict the time to initiate IGSCC vs. temperature and loading for a weld 182 having a high susceptibility to SCC crack growth. The effect of cyclic loading, strain path and dendrite orientation on initiation was also partly evaluated. Under static loading, initiation was observed down to 350 MPa at 360°C. A limited effect of cyclic loading (R = 0.9, f = 2.8 10−4 Hz) was observed at 360°C for a maximal stress of 350 MPa. The effect of partial periodic loading increased when the temperature decreased and when the stress increased. An empirical model predicting the time to SCC initiation was calibrated.
This is a preview of subscription content, log in via an institution to check access.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Preview
Unable to display preview. Download preview PDF.
Similar content being viewed by others
References
P. Scott ET al, ‘Comparison of laboratory and field experience of PWSCC in alloy 182 weld metal’, 13rd International Conference on environmental degradation of materials in nuclear systems-water reactors, Whistler (Canada), 2007.
J.-M. Boursier, F. Vaillant, B. Yrieix, T. Couvant, ‘Weldability, thermal ageing and PWSCC behavior of nickel weld metals containing 15 to 30% chromium’, PVP 2004, San Diego.
F. Vaillant et al., ‘A review of weldability and SCC behaviors of Ni-base weld metals in laboratory PWR environment’, 13rd International Conference on environmental degradation of materials in nuclear systems-water reactors, Whistler (Canada), 2007.
T. Couvant, F. Vaillant, E. Lemaire, ‘Stress corrosion crack growth rate in rolled alloy 600 exposed to primary PWR environment’, 14th International conference on environmental degradation of materials in nuclear power systems-water reactor, Virginia Beach (USA), 2009.
T. Couvant, L. Legras, A. Herbelin, A. Musienko, G. Ilevbare, D. Delafosse, G. Cailletaud, J. Hickling, ‘Development of understanding of the interaction between localized deformation and SCC of austenitic stainless steels exposed to primary PWR environment’, 14th International Conference on environmental degradation of materials in nuclear systems-water reactors, Virginia Beach (Virginia), 2009.
T. Couvant, L. Legras, T. Ghys, N. Huin, P. Gambier, G. Ilevbare, ‘Strain path effect on SCC initiation and oxidation of Ni base alloys exposed to PWR primary water’, 14th International Conference on environmental degradation of materials in nuclear systems-water reactors, Colorado Spring (USA), 2011.
T. Couvant, L. Legras, F. Vaillant, J.M. Boursier, Y. Rouillon, ‘Effect of strainhardening on stress corrosion cracking of AISI 304L stainless steel in PWR environment at 360°C’, 12th International Conference on environmental degradation of materials in nuclear systems-water reactors, Snowbird (USA), 2005.
F. Vaillant ET Al., ‘Influence of a cyclic loading on crack growth rates of alloy 600 in primary environment: an overview’, 11th International Conference on environmental degradation of materials in nuclear systems-water reactors, Stevenson, 2003.
F. Vaillant, J.-M. Boursier, T. Couvant, C. Amzallag, J. Champredonde, ‘Influence of a cyclic loading on the initiation and propagation of PWSCC in weld metal 182’, 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Snowbird (UA), 2005.
P. Scott, M. Foucault, B. Brugier, J. Hickling, A. Mc Ilree, ‘Examination of stress corrosion cracks in alloy 182 weld metal after exposure to PWR primary water’, 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Snowbird (USA), 2005.
T. Couvant, T. Brossier, C. Cossange, ‘PWSCC Susceptibility in Heat Affected Zones of Alloy 600’, 15th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Colorado Spring (USA), 2011.
Author information
Authors and Affiliations
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2011 TMS (The Minerals, Metals & Materials Society)
About this paper
Cite this paper
Couvant, T., Vaillant, F. (2011). Initiation of PWSCC of Weld Alloy 182. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_69
Download citation
DOI: https://doi.org/10.1007/978-3-319-48760-1_69
Publisher Name: Springer, Cham
Online ISBN: 978-3-319-48760-1
eBook Packages: Chemistry and Materials ScienceChemistry and Material Science (R0)