1. Thermal expansion of some cubic refractory compounds of thorium;Aronson;J. Am. Ceram. Soc.,1967
2. Artioli, C., Grasso, G., Sarotto, M., Krepel, J., 2009. ELSY Neutronic Analysis by Deterministic and Monte Carlo methods: An Innovative Concept for The Control Rod Systems. ICAPP 2009, May 10–14, Tokyo, Japan.
3. Aufiero, M., Cammi, A., Fiorina, C., Leppänen, J., Luzzi, L., Submitted for Publication. An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast Reactor. Submitted to Journal of Nuclear Materials. Presentation at NuMat 2012 Conference, October 22–25, Osaka, Japan.
4. Dobson, A., 2008. GNEP Deployment Studies Preliminary Conceptual Design Studies. Technical Report. Volume IV – Advanced Recycling Reactor.
5. Fiorina, C., Franceschini, F., Krepel, J., Mikityuk, K., 2011. Comparative analysis of uranium and thorium fuel cycles in a Lead-cooled Fast Reactor from the perspective of safety and waste management. GLOBAL 2011, December 11–16, Chiba, Japan.