1. P.M. Scott et al., in Comparison of Laboratory and Field Experience of PWSCC in Alloy 182 Weld Metal. Proceedings of the 13th International Conf. On Environment Degradation of Materials in Nuclear Power Systems-Water Reactors (Whistler, British Columbia, 2007)
2. J. Hickling, A. Mcllree, R. Pathania, Materials reliability program (MRP) crack growth rates for evaluating primary water stress corrosion cracking (PWSCC) of thick-wall Alloy 600 materials (MRP-55). Revision 1, EPRI, Palo Alto, CA, EPRI Final Report (1006695), (2002)
3. G.A. White, J. Hickling, L.K. Mathews, in Crack Growth Rates for Evaluating PWSCC of Thick-Wall Alloy 600 Material. Proceedings of the 11th International Conf. On Environmental Degradation Materials Nuclear Power Systems-Water Reactors, (ANS, 2003), pp. 166–179
4. S. Yamazaki et al., The effect of prior deformation on stress corrosion cracking growth rates of Alloy 600 materials in a simulated pressurized water reactor primary water. Corros. Sci. 50, 835–846 (2008)
5. M. Sennour et al., Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment. J. Nucl. Mater. 393, 254–266 (2009)