1. Global thermodynamic approach of the molten core-concrete interaction (MCCI) and selected applications in the nuclear field
2. B. Adroguer, G. Azarian, M. Barrachin, M. Bellon, D. Bottomley, P.Y. Chevalier, B. Cheynet, G. Cognet, M. Coquerelle, M. Fischer, K. Forcey, P. Hofman, S. Hellmann, S. Marget, R. Nannicini, J.M. Seiler, P. Pacenti, M. Steinbrück, F. Toci, Corium interactions and thermochemistry (CIT Project), In-vessel core degradation and coolability (INV cluster), In and ex-vessel corium properties and thermochemistry, Fisa-1999, EU Research in Reactor Safety, EC, Luxembourg, 29 November–1 December, 1999
3. A. De Bremaecker, M. Barrachin, L. Belovsky, P.Y. Chevalier, B. Cheynet, F. Defoort, P.H. Duvigneaud, K. Froment, F. Funke, S. Hellmann, Z. Hozer, F. Jacq, C. Journeau, S. Marguet, P. Mason, K. Mwamba, M. Mignanelli, P. Piluso, C. Ronneau, L. Sannen, M. Verwerft, V. Vrilkova, European nuclear thermodynamic database for in & ex-vessel applications (ENTHALPY), Fisa-2003, EU Research on Severe Accidents, EC, Luxembourg, 10–13 November, 2003
4. Thermodynamic modelling of the O–U–Zr system