CINECA IRIS Institutional Research Information System

D'AURIA, FRANCESCO SAVERIO
 Distribuzione geografica
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Continente #
NA - Nord America 54.179
EU - Europa 28.889
AS - Asia 12.867
AF - Africa 472
SA - Sud America 331
OC - Oceania 172
Continente sconosciuto - Info sul continente non disponibili 42
Totale 96.952
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Nazione #
US - Stati Uniti d'America 51.680
IT - Italia 10.782
CN - Cina 6.321
SE - Svezia 4.429
BG - Bulgaria 3.294
CA - Canada 2.463
UA - Ucraina 2.244
DE - Germania 1.912
VN - Vietnam 1.379
SG - Singapore 1.368
GB - Regno Unito 1.311
TR - Turchia 1.141
CH - Svizzera 1.114
FI - Finlandia 965
FR - Francia 769
RU - Federazione Russa 763
HK - Hong Kong 669
IR - Iran 479
KR - Corea 433
IN - India 290
JP - Giappone 230
ES - Italia 209
CI - Costa d'Avorio 203
AT - Austria 201
NL - Olanda 175
BE - Belgio 160
BR - Brasile 152
AU - Australia 151
HU - Ungheria 125
AR - Argentina 118
ID - Indonesia 103
CZ - Repubblica Ceca 100
RO - Romania 90
BJ - Benin 82
PK - Pakistan 82
IL - Israele 56
TW - Taiwan 48
UZ - Uzbekistan 43
EU - Europa 40
MY - Malesia 39
NO - Norvegia 38
PL - Polonia 36
EG - Egitto 34
GR - Grecia 33
DZ - Algeria 31
PH - Filippine 30
MX - Messico 29
SN - Senegal 27
ZA - Sudafrica 27
IE - Irlanda 26
SA - Arabia Saudita 25
JO - Giordania 23
PE - Perù 21
AE - Emirati Arabi Uniti 20
NZ - Nuova Zelanda 20
PT - Portogallo 19
BD - Bangladesh 18
SK - Slovacchia (Repubblica Slovacca) 18
DK - Danimarca 17
CO - Colombia 16
KZ - Kazakistan 14
HR - Croazia 12
NG - Nigeria 12
SI - Slovenia 12
TH - Thailandia 12
CL - Cile 11
GH - Ghana 10
SD - Sudan 10
RS - Serbia 9
SC - Seychelles 9
AF - Afghanistan, Repubblica islamica di 8
KE - Kenya 7
LU - Lussemburgo 7
EC - Ecuador 6
GE - Georgia 6
LY - Libia 6
AM - Armenia 5
MO - Macao, regione amministrativa speciale della Cina 5
EE - Estonia 4
IQ - Iraq 4
IS - Islanda 4
AZ - Azerbaigian 3
BY - Bielorussia 3
LK - Sri Lanka 3
LT - Lituania 3
UG - Uganda 3
VE - Venezuela 3
BA - Bosnia-Erzegovina 2
BO - Bolivia 2
DM - Dominica 2
ET - Etiopia 2
HN - Honduras 2
KW - Kuwait 2
OM - Oman 2
PY - Paraguay 2
XK - ???statistics.table.value.countryCode.XK??? 2
AL - Albania 1
AO - Angola 1
BN - Brunei Darussalam 1
BT - Bhutan 1
Totale 96.934
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Città #
Woodbridge 10.131
Ann Arbor 6.546
Houston 4.943
Milan 4.687
Sofia 3.286
Jacksonville 3.094
Chandler 3.052
Fairfield 2.598
Ottawa 2.253
Ashburn 1.972
Beijing 1.904
New York 1.830
Serra 1.637
Boardman 1.514
Princeton 1.505
Wilmington 1.263
Lawrence 1.241
Nanjing 1.102
Seattle 1.052
Bern 1.030
Izmir 872
Cambridge 859
Singapore 762
Des Moines 730
Medford 671
Dong Ket 632
Dearborn 614
Chicago 566
Jüchen 548
Redwood City 439
Rome 429
Nanchang 419
Hong Kong 384
Boulder 375
London 257
Changsha 227
Kunming 223
Shanghai 213
Guangzhou 212
Abidjan 203
Shenyang 197
San Diego 189
Hebei 172
Vienna 166
Düsseldorf 158
Tianjin 144
Los Angeles 143
Norwalk 135
Wuhan 135
Ogden 134
Washington 128
Hefei 125
Brussels 124
Jiaxing 121
Bremen 98
Gif-sur-yvette 98
Hangzhou 93
Kocaeli 92
Buenos Aires 85
Cotonou 82
Falls Church 79
Orange 76
Jinan 75
Pisa 75
Fremont 71
Frankfurt am Main 70
Indiana 69
Montecatini Terme 69
Tokyo 67
Central 66
San Jose 65
Chengdu 64
Verona 61
Auburn Hills 58
Helsinki 57
Paris 55
Moscow 51
Lanzhou 50
Central District 48
Xian 48
Zhengzhou 48
Barcelona 47
Istanbul 47
Brisbane 46
Seoul 45
Phoenix 43
Chongqing 42
West Jordan 42
San Francisco 41
Grafing 40
Madrid 39
Council Bluffs 38
Mumbai 38
Tappahannock 38
Dallas 35
Paks 35
Amsterdam 34
Turin 34
Livorno 32
Ankara 31
Totale 70.963
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Nome #
An overview of Thorium Utilization in Nuclear Reactors and Fuel Cycle 1.177
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series 657
Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants 479
Scaling in System Thermal-Hydraulics Applications to Nuclear Reactor Safety and Design: a State-of-the-Art Report. 342
Deterministic Safety Analysis for Nuclear Power Plants. IAEA Specific Safety Guide 265
Insights into BEPU 243
OECD/NEA/CSNI/WGAMA PERSEO benchmark: main outcomes and conclusions 224
A general method of predicting critical heat flux in Advanced Water Cooled Reactors 221
"Blowdown experiments from a pressure vessel with internal structures" (in Italian), University of Pisa Report, IIN - RL 317(78), Pisa (I), 199
A proposed Methodology for the Analysis of a Phenomenon in Separate Effects and Integral Test Facilities 197
Neutronics/Thermal-hydraulics Coupling in LWR Technology – CRISSUE-S WP3: Achievements and Recommendations Report 194
"Proposal of planning hydrogen related experiences in PIPER-ONE facility", University of Pisa Report, DCMN - NT 001(82), Pisa (I) 193
Post-BEMUSE Reflood Model input uncertainty methods (PREMIUM) Benchmark Phase II: identification of influential Parameters 191
Numerical Simulation of Free Surface Flows With Heat and Mass Transfer 188
OECD CSNI ISP 15: pre-test analysis of a split break transient in FIX-II loop performed at Pisa University by RELAP4/MOD6 code 188
Analysis by RELAP4/MOD6 code of the reference transient in the design of PIPER-ONE loop" (in Italian), University of Pisa Report, IIN - RP 492(81), Pisa (I), 188
Methodology for the evaluation of the reliability of passive systems 188
Blowdown two-phase flowrate evaluation from pressure and thrust measurements 185
PIPER-ONE loop: simulation of heat transfer between fluid and structures during a SBLOCA in a BWR" (in Italian) 185
LOBI test B-302: electric power evaluation and pre-test analysis performed by RELAP4/MOD6 computer code", University of Pisa Report, DCMN - RP 002(82), Pisa (I) 182
"Thermo-mechanical design of the core of PEC Fast Reactor" (in Italian) - CNEN-DRV Report VT.CC.00065, Bologna (I), Apr. 1978 180
Methodology for the reliability evaluation of a passive system and its integration into a Probabilistic Safety Assessment 174
A procedure to optimize the timing of operator actions of accident management procedures 174
Post-test analysis of LOBI test SD-SL-03 performed by RELAP4/MOD6 code 171
A model for the analysis of pump start-up transients in Tehran Research Reactor 170
Italian point of view in assessment and validation of large thermal-hydraulic computer codes", University of Pisa Report, DCMN - RL 070(83), Pisa (I), Dec. 1983, 3rd Meet. of the CSNI SACTE Task Group, Paris (F), Nov. 30-Dec. 3, 1983 169
Natural Circulation Phenomena and Modeling for Advanced Water Cooled Reactors 168
V & V in System Thermal-Hydraulics 166
PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review 166
Loss of Coolant Accident: parametric analysis of the initial period of the depressurization of a BWR vessel with the use of the RELAP4/MOD5 code" (in Italian) 166
Problems in the evaluation of thrusts during a Loss of Coolant Accident in a Light Water Reactor" (in Italian) 165
Thermal-hydraulic performance of primary system of RBMK in case of accidents 163
Feasibility analysis of PIPER-ONE loop: a system to simulate SBLOCA in BWRs" (in Italian), University of Pisa Report, IIN - RP 416(80), Pisa (I), Sept. 1980 163
"Determination of electrical power to be supplied to LOBI heaters", University of Pisa Report, DCMN - NT 011(80), Pisa (I), June 1980 162
ATLAS Program & Physical Models of SPACE, Critical evaluation of current status 162
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation 161
Validation of NEPTUNE CFD Module with Data of a Plunging Water Jet Entering a Free Surface 161
OECD CSNI ISP 15: post-test analysis of a split break transient in FIX-II loop performed at Pisa University by RELAP4/MOD6 and RELAP5/MOD1 codes", University of Pisa Report, DCMN - RL 067(83), Pisa (I), Dec. 1983, OECD CSNI Workshop on ISP 15, Nykoping (S), Dec. 15-16, 1983 161
Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled Thermal-Hydraulic 3D Kinetics code 160
MTR benchmark static calculations with MCNP5 code 158
Analysis of the influence of the upper downcomer nodalization on the LOBI test SD-SL-03 using RELAP4/MOD6 157
Density Measurements for Two-Phase Critical Flows" (in Italian), 38th Conf. Italian Thermo-technic Association (ATI), Bari (I), Sept. 28-30 1983 157
Scaling of Natural Circulation in PWR Systems 155
Uncertainties in Predictions by Thermal-Hydraulic Codes: Approaches and Results 155
Evaluation of uncertainties in system thermal-hydraulic calculations and key applications by the CIAU method 155
Brotini P., Carbone C., D'Auria F., DeSanti G., Mazzini M., Oriolo F., "LOBI test A2-55: electric power evaluation and preliminary analysis of results obtained by RELAP4/MOD6 code", University of Pisa Report, IIN - RP 472(81), Pisa (I) 154
Assessment of RELAP5/MOD2 Code on the Basis of Experiments Performed in LOBI Facility 153
The Individual Channel Monitoring (ICM) proposal to improve the safety performance of RBMK 153
Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code 152
A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP 152
Deterministic Safety Technology for RBMK Reactors 151
Safety Analysis for Research Reactors 151
Analyses of pressure perturbation events in boiling water reactor 151
Thermal-hydraulic design of PIPER-ONE loop", University of Pisa Report, DCMN - RL 003(82), Pisa (I) 151
Flowrate and Density Oscillations During Two-Phase Natural Circulation in PWR Typical Conditions 150
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures 149
Overview of accident analysis in nuclear research reactors 149
Critical Flow Modelling in Nuclear Safety 148
Analysis of the Peach Bottom flow stability test number 3 using the coupled RELAP5/PARCS code 148
Assessment of 12 CHF Prediction Methods, for an Axially Non-Uniform Heat Flux Distribution, with the RELAP5 Computer Code 148
Uncertainty and sensitivity analysis of the LOFT L2-5 test: Results of the BEMUSE programme 148
Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Tool 148
Density Wave Instabilities in Steam Generators 145
Assessment study of the coupled code Relap5/Parcs against the Peach Bottom BWR turbine trip test 145
FONESYS : The Forum & Network of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics 145
Design of PIPER-ONE loop -Final Version- " (in Italian) 145
A Procedure for Characterizing the Range of Input Uncertainty Parameters by the Use of FFTBM 145
Validation of Neptune CFD Module With Data of a Plunging Water Jet Entering a Free Surface 143
PERSEO Benchmark - UNIPI results 142
Scaling of complex phenomena in System Thermalhydraulics 141
Neutronics/Thermal-hydraulics Coupling in LWR Technology – CRISSUE-S WP1: Data Requirements and Databases Needed for Transient Simulations and Qualification 141
Application of an optimized AM procedure following a SBO in a VVER-1000 141
Assessment of RELAP5/MOD2 Code on the Basis of Experiments performed in LOBI Facility 140
A methodology for the qualification of thermalhydraulic codes Nodalizations 140
Sensitivity analysis of the Peach Bottom Turbine Trip 2 experiment 140
Use of coupled code technique for Best Estimate safety analysis of nuclear power plants 140
V&V&C in nuclear reactor thermal-hydraulics 140
Advancements in Evaluating Accuracy of Thermalhydraulic Codes Calculations 139
Deterministic accident analysis for RBMK 139
Determination of code accuracy in predicting small break LOCA experiment 137
Three-Dimensional Thermal-Hydraulics Analysis of ROCOM Mixing Experiment By Relap5-3d© Code 137
Application of CFX-10 to the investigation of RPV coolant mixing in VVER reactors 136
The BEMUSE Programme: Results of the first part concerning the LOFT L2-5 test 136
Application of REPAS Methodology to Assess the Reliability of Passive Safety Systems 136
Fluiddynamic Analysis of Steam-Water Flows from a Pressure Vessel 135
International training program: 3D SUNCOP – Scaling, Uncertainty and 3D thermal-hydraulic / Neutron kinetics coupled codes Seminar 135
Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core 135
Application of REPAS methodology to assess the reliability of passive safety systems 135
Thermal-Hydraulic Analysis of Coolant Flow Decrease in Fuel Channels of Smolensk-3 RBMK during GDH Blockage Event 135
CFD Analysis of a Slug Mixing Experiment Conducted on a VVER-1000 Model 135
Effect of Steam Generator Heat Transfer upon Core Reflood in a PWR 134
Report of the Uncertainty Methods Study for advanced best estimate thermalhydraulic code applications 134
Capabilities of Transuranus Code in Simulating Power Ramp Tests from the IFPE Database 134
The utilization of thorium in Small Modular Reactors – Part I: Neutronic assessment 134
Study on The Relap5 Break Models Making Reference to the Lobi BL-30 Experiment 133
Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis 133
Proposed Set of Criteria in Designing Nuclear Power Plants Experimental Simulators 132
Main Results of Phase IV BEMUSE Project. Simulation of LBLOCA in a NPP 132
The REPAS study: Reliability evaluation of passive safety systems 131
RBMK Fuel Channel Blockage Reactivity Analysis by MCNP5 and RELAP5-3D© codes 131
Totale 17.772
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Categoria #
all - tutte 229.458
article - articoli 0
book - libri 0
conference - conferenze 0
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 0
Totale 229.458
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20209.793 0 0 1.620 619 1.147 1.113 1.347 595 1.203 735 1.215 199
2020/20218.578 824 219 755 339 860 524 759 650 622 840 447 1.739
2021/202213.257 305 1.035 324 924 2.700 2.150 305 661 513 322 789 3.229
2022/20239.882 1.801 810 501 948 1.392 1.452 266 754 1.249 105 406 198
2023/202416.125 2.625 1.920 1.945 1.255 2.283 2.310 338 407 291 565 350 1.836
2024/20252.502 498 1.742 262 0 0 0 0 0 0 0 0 0
Totale 98.613