1. M. Zbinden, V. Durbec, A kinetic model for impact/sliding wear of pressurized water reactor internal components: application to rod cluster control assemblies, in: Proceedings of the ASME Pressure Vessels and Piping Conference, Montreal, 1996.
2. P. Ko, M.C. Taponat, M.F. Robertson, M. Zbinden, Friction and wear studies of nuclear power plant components in pressurized high temperature water environments, in: Proceedings of the ASME Pressure Vessels and Piping Conference, Montreal, 1996.
3. D. Moinereau, A. Lina, D. Hersant, M. Zbinden, Experimental study of impact/sliding wear of rod cluster control assemblies of PWR nuclear power plants, in: Proceedings of the 8th International Conference on Nuclear Engineering, ICONE 8, Baltimore, 2000.
4. F. Guérout, N. Fisher, Steam generator fretting-wear damage: a summary of recent findings, in: Proceedings of the ASME Pressure Vessels and Piping Conference, Boston, 1999.
5. A. Lina, M. Zbinden, D. Hersant, Méthodes de mesures tribologiques associées aux essais d’usure des composants internes des réacteurs nucléaires à eau pressurisée’, Actes des Journées d’Etudes de la Société Tribologique de France SFT 97, 1997.