1. M. Bioulac, M.F. Cipiere, G. Poudroux, F. Champigny, L. Mercier, Y. Rouillon, F. Vaillant, Replacement of alloy 600 by alloy 690 for steam generator tubes and closure heads in PWR, in: Rep. INIS-FR--4141, INIS, Paris, France, 2004: pp. 179–188. http://inis.iaea.org/Search/search.aspx?orig_q=RN:37040643.
2. N. Engler, C. Brun, M. Guillodo, Optimization of SG Tubes Prefilming Process to Reduce Nickel Release, in: NPC 08 Int. Conf. Water Chem. Nucl. React. Syst., VGB Powertech, Berlin, Germany, 2008: pp. 251–256. https://www.vgb.org/shop/buecher/tagungsbande/tb430-08-cd.html.
3. Analysis and TEM examination of corrosion scales grown on Alloy 690 exposed to pressurized water at 325 °C;Carrette;Surf. Interf. Anal.,2002
4. Electrochemical characterization of oxide film formed at high temperature on Alloy 690;Abraham;Nucl. Eng. Des.,2012
5. General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants;Scott;J. Nucl. Mater.,2019