D'AURIA, FRANCESCO SAVERIO Statistiche

D'AURIA, FRANCESCO SAVERIO  

DIPARTIMENTO DI INGEGNERIA DELL'ENERGIA, DEI SISTEMI, DEL TERRITORIO E DELLE COSTRUZIONI  

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Titolo Data di pubblicazione Autore(i) File
11% upper plenum break (in PSB facility): application of Relap5-3D © and comparison with other codes 1-gen-2004 DEL NEVO, A.; Cherubini, M.; Araneo, D.; D'Auria, FRANCESCO SAVERIO; Galassi, G. M.
[116] THERMAL-HYDRAULIC PHENOMENA 1-gen-2018 Aksan, N.; D'Auria, F.; Glaeser, H.
3-D Noding of reactor pressure vessel downcomer suitable for CFD codes 1-gen-2000 Magliolo, P; D'Auria, FRANCESCO SAVERIO
A methodology for the qualification of thermalhydraulic codes Nodalizations 1-gen-1992 Bonuccelli, M; D'Auria, FRANCESCO SAVERIO; Debrecin, N; Galassi, G. M.
A general method of predicting critical heat flux in Advanced Water Cooled Reactors 1-gen-1999 Groeneveld, D. C.; Leung, L. K. H.; Aksan, N.; Badulescu, A.; Cleveland, J.; Baek, W. P.; Chung, M. K.; D'Auria, FRANCESCO SAVERIO; Cheng, X.; Kirillov, P.; Macek, J.
A proposed Methodology for the Analysis of a Phenomenon in Separate Effects and Integral Test Facilities 1-gen-1995 D'Auria, FRANCESCO SAVERIO; Faluomi, V.; Aksan, S. N.
A Comparison and Assessment of some Critical Heat Flux Prediction Models used in Thermal-hydraulic System Codes 1-gen-1994 Faluomi, V; D'Auria, FRANCESCO SAVERIO; Aksan, S. N.
A mechanistic model for counter-current flow at the Upper Tie Plate 1-gen-1990 Ambrosini, Walter; D'Auria, FRANCESCO SAVERIO; A., Soldati
A model for the analysis of pump start-up transients in Tehran Research Reactor 1-gen-2007 Farhadi, K.; BOUSBIA SALAH, A.; D'Auria, FRANCESCO SAVERIO
A novel methodology of internal assessment of uncertainty for coupled three-dimensional neutronics thermal-hydraulics system codes 1-gen-2003 Petruzzi, A; D'Auria, FRANCESCO SAVERIO; Ivanov, K.
A novel methodology of internal assessment of uncertainty for three-dimensional neutronics thermal-hydraulics system codes 1-gen-2003 Petruzzi, A; D'Auria, FRANCESCO SAVERIO; Ivanov, K.
A pilot application of Relap code to the steady state and transient analysis of a test section inside the BR2 reactor 1-gen-2000 FERRI M., G; D'Auria, FRANCESCO SAVERIO; Forasassi, G; Giot, M.
A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP 1-gen-2011 Adorni, M.; DEL NEVO, A.; D'Auria, FRANCESCO SAVERIO; Mazzantini, O.
A procedure to optimize the timing of operator actions of accident management procedures 1-gen-2007 Muellner, N; Cherubini, M; Kromp, W; D'Auria, FRANCESCO SAVERIO; Petrangeli, G.
A procedure to optimize the timing of operator actions of Accident Management procedures 1-gen-2006 D'Auria, FRANCESCO SAVERIO; Muellner, N; Cherubini, M; Kromp, W; Petrangeli, G.
A PWR recovery option for a total loss of feedwater beyond design basis scenario 1-gen-2003 Madeira, A; D'Auria, FRANCESCO SAVERIO; Alvim, A. C. M.
A sensitivity study on the performance of a passive system 1-gen-2003 Caruso, G; D'Auria, FRANCESCO SAVERIO
A verification or Relap5/mod2 Code using OECD CSNI ISP 26 Standard Problem Calculation (in Croatian) 1-gen-1991 Debrecin, N; Grgic, D; Bajs, T; Spalj, S; Cavlina, N; D'Auria, FRANCESCO SAVERIO
Accident Analysis for Nuclear Power Plants 1-gen-2002 Allison, C.; Balabanov, E.; D'Auria, FRANCESCO SAVERIO; Jankowski, M.; Misak, J.; Salvatores, S.; Snell, V.
Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water Reactors 1-gen-2003 Allison, C.; Balabanov, E.; D'Auria, FRANCESCO SAVERIO; Jankowski, M.; Misak, J.; MUNOZ CAMARGO, C.; Salvatores, S.; Snell, V.