1. Ilevbare G. ‘Comments on contribution of cold work to SCC of stainless steels in a PWR primary circuit’, Proc. EPRI/AECL Workshop on ‘Cold work and its impact on components in light water nuclear reactors’, Toronto, Ont., Canada, June 2007, EPRI/AECL.
2. Emerging Issues and Fundamental Processes in Environmental Cracking in Hot Water
3. Shoji T., Li G., Kwon J., Matsushima S. and Lu Z. ‘Quantification of yield stress effects on IGSCC of austenitic stainless steels in high temperature water’, Proc. 11th Int. Conf. on ‘Environmental degradation of materials in nuclear power systems’, Stevenson, AL, USAAugust 2003, ANS, 834–844.
4. Guerre C., Herms E., Raquet O. and Marie S. ‘SCC crack growth rate of cold-worked austenitic stainless steels in PWR primary water conditions’, Proc. 13th Int. Conf. on ‘Environmental degradation of materials in nuclear power systems’, Vancouver, BC, Canada, August 2007, CNS, 1–24.
5. Tice D. R., Stairmand J., Fairbrother H. and Stock A. ‘Crack growth testing of cold worked stainless steel in a simulated PWR primary water environment to assess susceptibility to stress corrosion cracking’, Proc. 13th Int. Conf. on ‘Environmental degradation of materials in nuclear power systems’, Vancouver, BC, Canada, August 2007, CNS, 1–17.