1. Joshua K. McKinley, et al., Comparison of Boiling Water Reactor and Pressurized Water Reactor Experience with Cracking of Austenistic Stainless Steel. 2018(SCC): p. 17.
2. Agency, I.A.E., Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internal. 1999(IAEA-TECDOC-1119).
3. K.H. Luk, O.R.N.L., Pressurized-Water Reactor Internals Aging Degradation Study. NUREG/CR-6048, 1993. ORNU-TM-12371.
4. Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension;Hojná;Corrosion,2013
5. Morgane Le Millier, O.C., Jérôme Crépin, Cécilie Duhamel, Fabrice Gaslain, Eva Heripre, Ovidiu Toader, Yoann Vidalenc, Irradiation assisted stress corrosion cracking of stainless steels in a PWR environment. 15th International Conference on Environmental Degradation, 2011.