1. Accident analysis for nuclear power plants,2002
2. A review of ccfl phenomenon;Al Issa;Annals of Nuclear Energy - ANN NUCL ENERG,2011
3. CSNI integral test facility validation matrix for the assessment of thermal-hydraulic codes for LWR LOCA and transients;Annunziato,1996
4. Caracterizacion De La Evaluacion De Seguridad Del Reactor De Seguridad WWER-1000 Mediante Metodología ”Best Estimate” Con Analisis De Incertidumbres;Berthon,2005
5. Bonuccelli, M., D’Auria, F., N., D., Giorgio, G., 1993. A methodology for the qualification of thermalhydraulic codes nodalizations. In: International Topical Meeting on Nuclear Reactor Thermal Hydraulics 1993, NURETH-6.