1. Electrochemical behaviour of stainless steel in PWR primary coolant conditions: Effects of radiolysis
2. A prediction model of IASCC initiation stress for bolts in PWR core internals
3. G.O. Ilevbare, F. Cattant, N.K. Peat, in: Proceedings of the 7th International Conference on Contribution of Materials Investigations to Improve the Safety and Performance of LWRs, Fontevraud 7, 26–30, September 2010.
4. T. Couvant, P. Moulart, L. Legras, P. Bordes, J. Capelle, Y. Rouillon, T. Balon, in: Proc. 13th Int. Conf. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors. CNS, 2007, CDROM.
5. Stress corrosion cracking of uni-directionally cold worked 316NG stainless steel in simulated PWR primary water with various dissolved hydrogen concentrations