1. Cfd and dns methodologies development for fuel bundle simulations;Baglietto;Nuclear Engineering and Design,2006
2. Batta A, Zeininger J., Stieglitz R., 2009. Experimental and numerical investigation of turbulent liquid metal heat transfer along a heated rod in annular cavity, 2009 Internat. Congress on Advances in Nuclear Power Plants (ICAPP ’09), Tokyo, J, May 10–14, 2009 Proc.on CD-ROM Paper 9439 Tokyo: Atomic Energy Society of Japan, 2009, 32.26.02; LK 01.
3. Benhamadouche S., Le-Maitre C., Large eddy simulation of the flow along four sub-channels downstream a mixing grid in a pwr, NURETH13, Kanazawa, Japan.
4. Bornia G., Cerroni D., Finelli M., Ghiselli L., Manservisi S., Martinotti C., Menghini F., Scardovelli R. Report on validation of heat transfer correlations on single rod data and on rod bundle data, THINS (Thermal Hydraulics of Innovative Nuclear Systems) WP 1 Advance Reactor Core thermal-hydraulics. Technical Report D.1.1.09.