1. Appendix ZG to RCC-M (Design and Construction Rules for Mechanical Components of PWR Nuclear Islands), 1988 Edition, Association Française pour les Règles de Conception et de Construction des Matériels Electro-Nucléaires, Paris.
2. French verification of PWR vessel integrity;Pellissier-Tanon;Report EPRI NP 6713,1990
3. Accurate fracture mechanics analysis methods for subsurface or surface defects, including their interacton with the cladding;Pellissier-Tanon;Int. J. Pres. Ves. & Piping,1993
4. In-service evaluation of french pressurized water reactor vessel steel;Brillaud;ASTM STP 1125,1992
5. Analysis of irradiation embrittlement results from a french forging examined in the second phase of an AIEA co-ordinated research program;Soulat;ASTM STP 1170,1993