P. Scott and M. L. Calvar, Some possible mechanisms of intergranular stress corrosion cracking of Alloy 600 in PWR primary water, 6th International Symposium on Environmental Degradation of Materials in Nuclear Power systems-Water Reactors, 1993.

D. K. Schreiber, M. J. Olszta, and S. M. Bruemmer, Grain boundary depletion and migration during selective oxidation of Cr in a Ni-5Cr binary alloy exposed to high-temperature hydrogenated water, Scr. Mater, vol.89, pp.41-44, 2014.

Y. S. Lim, S. W. Kim, S. S. Hwang, H. P. Kim, and C. Jang, Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment, Corros. Sci, vol.108, pp.125-133, 2016.

L. E. Thomas and S. M. Bruemmer, High-resolution characterization of intergranular attack and stress corrosion cracking of Alloy 600 in high-temperature primary water, Corrosion, vol.56, pp.572-587, 2000.

M. Sennour, P. Laghoutaris, C. Guerre, and R. Molins, Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment, J. Nucl. Mater, vol.393, pp.254-266, 2009.
URL : https://hal.archives-ouvertes.fr/hal-00423736

D. K. Schreiber, M. J. Olszta, D. W. Saxey, K. Kruska, K. L. Moore et al., Examinations of oxidation and sulfidation of grain boundaries in Alloy 600 exposed to simulated pressurized water reactor primary water, Microsc. Microanal, vol.19, pp.676-687, 2013.

K. Kruska, P. Chou, O. Calonne, L. Fournier, and S. Lozano-perez, Atom-probe tomography of surface and grain boundary oxides in Alloy 600 and Alloy 690 exposed to simulated PWR primary water, 16th International Conference on the Environmental Degradation of Materials in Nuclear Power Systems, 2013.

M. J. Olszta, D. K. Schreiber, L. E. Thomas, and S. M. Bruemmer, Penetrative internal oxidation from Alloy 690 surfaces and stress corrosion crack walls during exposure to PWR primary water, 15th International Conference on the Environmental Degradation of Materials in Nuclear Power Systems, 2011.

C. Guerre, P. Laghoutaris, J. Chêne, L. Marchetti, R. Molins et al., Stress corrosion cracking of Alloy 600 in PWR primary water: influence of chromium, hydrogen and oxygen diffusion, 15th International Conference on the Environmental Degradation of Materials in Nuclear Power Systems, p.2011
URL : https://hal.archives-ouvertes.fr/hal-00683119

G. Bertali, F. Scenini, and M. G. Burke, Advanced microstructural characterization of the intergranular oxidation of Alloy 600, Corros. Sci, vol.100, pp.474-483, 2015.

G. Bertali, F. Scenini, and M. G. Burke, The intergranular oxidation susceptibility of thermallytreated Alloy 600, Corros. Sci, vol.114, pp.112-122, 2017.

A. H. King, Diffusion induced grain boundary migration, Int. Mater. Rev, vol.32, pp.173-189, 1987.
URL : https://hal.archives-ouvertes.fr/jpa-00230353

H. J. Frost and M. F. Ashby, Deformation-Mechanism Maps, 1982.

S. M. Daiser, C. Scholze, and J. L. Maul, The checkerboard technique: an essential progress in SIMS data acquisition and evaluation, Nucl. Instrum. Methods Phys. Res. Sect. B Beam Interact. Mater. At, vol.35, pp.544-549, 1988.

D. D. Pruthi, M. S. Anand, and R. P. Agarwala, Diffusion of chromium in Inconel 600, J. Nucl. Mater, vol.64, pp.206-210, 1977.

T. Chen, G. P. Tiwari, Y. Iijima, and K. Yamauchi, Volume and grain boundary diffusion of chromium in Ni-base Ni-Cr-Fe alloys, Mater. Trans, vol.44, pp.40-46, 2003.

H. Mehrer, Diffusion in Solids, 2007.

J. R??i?ková and B. , Million, Self-diffusion of the components in the FCC phase of binary solid solutions of the Fe-Ni-Cr system, Mater. Sci. Eng, vol.50, pp.59-64, 1981.

K. Monma, H. Suto, and H. Oikawa, Diffusion of Ni63 and Cr51 in nickel-chromium alloys, J. Jpn. Inst. Met, vol.28, pp.188-192, 1964.

M. Cohen, Self-diffusion during plastic deformation, Trans. Jpn. Inst. Met, vol.11, pp.145-151, 1970.

A. R. Wazzan and E. Dorn, Analysis of enhanced diffusivity in nickel, J. Appl. Phys, vol.36, pp.222-228, 1965.

E. Orowan, Problems of plastic glide, Proc. Phys. Soc, vol.52, pp.8-22, 1940.

C. Wagner, Theoretical analysis of the diffusion processes determining the oxidation rate of alloys, J. Electrochem. Soc, vol.99, pp.369-380, 1952.

H. Lefaix-jeuland, L. Marchetti, S. Perrin, M. Pijolat, M. Sennour et al., Oxidation kinetics and mechanisms of Ni-base alloys in pressurised water reactor primary conditions: influence of subsurface defects, Corros. Sci, vol.53, pp.3914-3922, 2011.
URL : https://hal.archives-ouvertes.fr/hal-00628750

S. L. Hong, C. Amzallag, and A. Gelpi, Modelling the SCC initiation on alloy 600 in primary water of PWRs, 9th International Conference on the Environmental Degradation of Materials in Nuclear Power Systems, 1999.