CINECA IRIS Institutional Research Information System

D'AURIA, FRANCESCO SAVERIO
 Distribuzione geografica
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Continente #
NA - Nord America 76.350
AS - Asia 50.527
EU - Europa 35.432
SA - Sud America 7.893
Continente sconosciuto - Info sul continente non disponibili 1.753
AF - Africa 1.133
OC - Oceania 292
Totale 173.380
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Nazione #
US - Stati Uniti d'America 73.071
CN - Cina 14.333
SG - Singapore 12.954
IT - Italia 11.555
HK - Hong Kong 9.297
BR - Brasile 6.321
SE - Svezia 4.530
VN - Vietnam 4.221
BG - Bulgaria 3.315
CA - Canada 2.808
KR - Corea 2.587
UA - Ucraina 2.348
DE - Germania 2.312
FR - Francia 2.249
RU - Federazione Russa 1.998
TR - Turchia 1.936
GB - Regno Unito 1.920
FI - Finlandia 1.546
CH - Svizzera 1.274
JP - Giappone 1.121
IN - India 913
AR - Argentina 661
IR - Iran 594
ID - Indonesia 428
BD - Bangladesh 427
NL - Olanda 407
AT - Austria 339
ES - Italia 330
AU - Australia 261
EC - Ecuador 259
HU - Ungheria 257
PK - Pakistan 221
BE - Belgio 215
IQ - Iraq 211
CI - Costa d'Avorio 208
MX - Messico 205
ZA - Sudafrica 198
CO - Colombia 182
SA - Arabia Saudita 168
CZ - Repubblica Ceca 146
UZ - Uzbekistan 141
MY - Malesia 131
PL - Polonia 112
RO - Romania 112
MA - Marocco 110
EG - Egitto 109
VE - Venezuela 108
PH - Filippine 102
PY - Paraguay 101
CL - Cile 98
IL - Israele 93
BJ - Benin 85
PE - Perù 85
TW - Taiwan 85
AE - Emirati Arabi Uniti 84
KE - Kenya 80
DZ - Algeria 72
JO - Giordania 72
NO - Norvegia 68
KZ - Kazakistan 66
JM - Giamaica 58
TH - Thailandia 57
IE - Irlanda 56
TN - Tunisia 50
GR - Grecia 49
NP - Nepal 48
UY - Uruguay 48
SN - Senegal 47
CR - Costa Rica 40
EU - Europa 40
PT - Portogallo 40
LT - Lituania 39
SK - Slovacchia (Repubblica Slovacca) 32
AZ - Azerbaigian 31
DK - Danimarca 30
ET - Etiopia 29
HN - Honduras 26
NZ - Nuova Zelanda 25
OM - Oman 25
SI - Slovenia 25
RS - Serbia 23
GH - Ghana 22
LB - Libano 22
NG - Nigeria 22
TT - Trinidad e Tobago 22
BO - Bolivia 21
DO - Repubblica Dominicana 21
AL - Albania 19
BY - Bielorussia 18
SY - Repubblica araba siriana 18
BB - Barbados 17
GE - Georgia 17
HR - Croazia 16
PS - Palestinian Territory 16
AO - Angola 15
KW - Kuwait 15
PA - Panama 15
LY - Libia 14
BH - Bahrain 12
GA - Gabon 11
Totale 171.391
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Città #
Woodbridge 10.134
Hong Kong 8.898
Singapore 7.511
Ashburn 6.752
Ann Arbor 6.546
Houston 5.008
Milan 4.790
Sofia 3.293
San Jose 3.156
Jacksonville 3.105
Chandler 3.052
Fairfield 2.600
Hefei 2.573
Dallas 2.543
Beijing 2.376
Shanghai 2.311
Ottawa 2.273
Seoul 2.034
New York 2.010
Serra 1.664
Boardman 1.528
Princeton 1.508
Santa Clara 1.336
Wilmington 1.278
Lawrence 1.243
Nanjing 1.110
Seattle 1.095
Lauterbourg 1.075
Ho Chi Minh City 1.047
Bern 1.030
Izmir 881
Council Bluffs 873
Cambridge 868
Los Angeles 863
Tokyo 825
Des Moines 745
Chicago 672
Medford 672
Hanoi 658
Istanbul 646
Dong Ket 632
Dearborn 616
Helsinki 563
Buffalo 552
Jüchen 548
Rome 512
São Paulo 496
Redwood City 440
Nanchang 424
Redondo Beach 411
Boulder 377
London 323
Guangzhou 303
Orem 300
Changsha 254
Vienna 238
Kunming 231
Rio de Janeiro 214
Abidjan 208
Shenyang 207
San Diego 193
Wuhan 173
Hebei 172
Düsseldorf 169
Paris 167
Tianjin 166
Frankfurt am Main 157
Zurich 157
Belo Horizonte 155
Brussels 150
Washington 149
Buenos Aires 147
Norwalk 139
Atlanta 135
Ogden 134
Brasília 124
Da Nang 124
Jiaxing 124
Munich 123
Haiphong 121
Manchester 121
Chennai 120
Hangzhou 111
Amsterdam 108
Tashkent 108
Mumbai 105
Porto Alegre 105
Budapest 104
Curitiba 101
Columbus 100
Dhaka 100
Bremen 98
Gif-sur-yvette 98
Phoenix 98
Brisbane 97
San Francisco 97
The Dalles 97
Nuremberg 95
Jinan 93
Pisa 93
Totale 115.459
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Nome #
An overview of Thorium Utilization in Nuclear Reactors and Fuel Cycle 2.426
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series 1.021
Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants 740
Scaling in System Thermal-Hydraulics Applications to Nuclear Reactor Safety and Design: a State-of-the-Art Report. 641
OECD/NRC PSBT Benchmark: Investigating the CATHARE2 Capability to Predict Void Fraction in PWR Fuel Bundle 533
Pressurized Heavy Water Reactors – Atucha II 526
"Proposal of planning hydrogen related experiences in PIPER-ONE facility", University of Pisa Report, DCMN - NT 001(82), Pisa (I) 498
OECD CSNI ISP 15: pre-test analysis of a split break transient in FIX-II loop performed at Pisa University by RELAP4/MOD6 code 492
Insights into BEPU 427
Deterministic Safety Analysis for Nuclear Power Plants. IAEA Specific Safety Guide 416
Atucha II Nuclear Reactor: Design Safety and Licensing 390
A general method of predicting critical heat flux in Advanced Water Cooled Reactors 366
"Blowdown experiments from a pressure vessel with internal structures" (in Italian), University of Pisa Report, IIN - RL 317(78), Pisa (I), 356
PIPER-ONE loop: simulation of heat transfer between fluid and structures during a SBLOCA in a BWR" (in Italian) 337
Comparison report of the OECD/CSNI International Standard Problem 21 (PIPER-ONE experiment SB-7) 335
Methodology for the evaluation of the reliability of passive systems 332
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), 328
"Thermo-mechanical design of the core of PEC Fast Reactor" (in Italian) - CNEN-DRV Report VT.CC.00065, Bologna (I), Apr. 1978 318
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) 317
Problems in the evaluation of thrusts during a Loss of Coolant Accident in a Light Water Reactor" (in Italian) 312
Post-BEMUSE Reflood Model input uncertainty methods (PREMIUM) Benchmark Phase II: identification of influential Parameters 311
OECD/NEA/CSNI/WGAMA PERSEO benchmark: main outcomes and conclusions 310
"Determination of electrical power to be supplied to LOBI heaters", University of Pisa Report, DCMN - NT 011(80), Pisa (I), June 1980 304
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) 301
PIPER-ONE test PO-SB-7c: post-test analysis performed by RELAP5/MOD2 code 298
ATLAS Program & Physical Models of SPACE, Critical evaluation of current status 298
PIPER-ONE research: boundary and initial conditions for OECD-CSNI International Standard Problem 21 (ISP 21) 296
Natural Circulation Phenomena and Modeling for Advanced Water Cooled Reactors 293
A proposed Methodology for the Analysis of a Phenomenon in Separate Effects and Integral Test Facilities 291
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) 290
PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review 289
Proposal of an International Standard Problem to be carried out in PIPER-ONE facility 287
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 287
Density Measurements for Two-Phase Critical Flows" (in Italian), 38th Conf. Italian Thermo-technic Association (ATI), Bari (I), Sept. 28-30 1983 287
PIPER-ONE research: experimental data report of PIPER-ONE test PO-SB-7, OECD CSNI 2nd Workshop on ISP 21, Calci (I), Apr. 13-14, 1989 287
PIPER-ONE Research: the experiment PO-SD-8 related to the evaluation of the Isolation Condenser performance. Post-test analysis carried out by RELAP5/MOD3-/7j Code 287
OECD CSNI ISP 21, PIPER-ONE test PO-SB-7: post test analysis performed at Pisa University by RELAP5/MOD2 code, OECD CSNI 2nd Workshop on ISP 21, Calci (I), Apr. 13-14, 1989 286
Post-test analysis of LOBI test SD-SL-03 performed by RELAP4/MOD6 code 284
PIPER-ONE research: available instrumentation and specifications for OECD-CSNI International Standard Problem 21 (ISP 21) 284
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 282
PIPER-ONE research: facility description for OECD-CSNI International Standard Problem N. 21 (ISP 21) 282
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 279
Analysis of the influence of the upper downcomer nodalization on the LOBI test SD-SL-03 using RELAP4/MOD6 277
Design of PIPER-ONE loop -Final Version- " (in Italian) 272
PIPER-ONE research: measured initial and boundary conditions for OECD CSNI International Standard Problem 21 (ISP 21) 271
Neutronics/Thermal-hydraulics Coupling in LWR Technology – CRISSUE-S WP3: Achievements and Recommendations Report 269
Blowdown two-phase flowrate evaluation from pressure and thrust measurements 269
NUREG/IA 0135 - Post-Test Analysis of PIPER-ONE PO-IC-2 Experiment by RELAP5/MOD3 Codes 267
Numerical Simulation of Free Surface Flows With Heat and Mass Transfer 266
Piper-one Research: overview of the experiments carried out and lesson learned 264
Preliminary planning of BIP tests to be performed in PIPER-ONE apparatus 259
Thermal-hydraulic design of PIPER-ONE loop", University of Pisa Report, DCMN - RL 003(82), Pisa (I) 252
A methodology for the qualification of thermalhydraulic codes Nodalizations 251
V & V in System Thermal-Hydraulics 247
V&V&C in nuclear reactor thermal-hydraulics 247
Conversion of Small Modular Reactors Fuel to Use Mixed (U-Th)O2 Fuel 247
Nuclear Energy and its History: Past Consequences, Present Inadequacies and a Perspective for Success 247
Methodology for the reliability evaluation of a passive system and its integration into a Probabilistic Safety Assessment 240
Neutronics/Thermal-hydraulics Coupling in LWR Technology – CRISSUE-S WP1: Data Requirements and Databases Needed for Transient Simulations and Qualification 237
Safety Analysis for Research Reactors 231
Assessment of RELAP5/MOD2 Code on the Basis of Experiments Performed in LOBI Facility 227
A model for the analysis of pump start-up transients in Tehran Research Reactor 225
A procedure to optimize the timing of operator actions of accident management procedures 225
PERSEO Benchmark - UNIPI results 225
Critical Flow Modelling in Nuclear Safety 217
Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled Thermal-Hydraulic 3D Kinetics code 217
Deterministic Safety Technology for RBMK Reactors 214
Uncertainty Methods and Approaches in Nuclear System Safety 214
Assessment of RELAP5/MOD2 Code on the Basis of Experiments performed in LOBI Facility 213
Sensitivity analysis of the Peach Bottom Turbine Trip 2 experiment 213
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation 213
Advancements in Evaluating Accuracy of Thermalhydraulic Codes Calculations 211
Thermal Hydraulics in Water-Cooled Nuclear Reactors 211
Evaluation of the accuracy of code calculations 210
Validation of NEPTUNE CFD Module with Data of a Plunging Water Jet Entering a Free Surface 210
Scaling of Natural Circulation in PWR Systems 208
Scaling Issues for the Experimental Characterization of Reactor Coolant System in Integral Test Facilities and Role of System Code as Extrapolation Tool 208
A Procedure for Characterizing the Range of Input Uncertainty Parameters by the Use of FFTBM 208
Flowrate and Density Oscillations During Two-Phase Natural Circulation in PWR Typical Conditions 207
Report of the Uncertainty Methods Study for advanced best estimate thermalhydraulic code applications 207
V&V and more in Nuclear Thermal-Hydraulics 207
Analyses of pressure perturbation events in boiling water reactor 206
Fluiddynamic Analysis of Steam-Water Flows from a Pressure Vessel 205
Thermal-hydraulic performance of primary system of RBMK in case of accidents 205
MTR benchmark static calculations with MCNP5 code 204
The Individual Channel Monitoring (ICM) proposal to improve the safety performance of RBMK 203
Analysis of the Peach Bottom flow stability test number 3 using the coupled RELAP5/PARCS code 202
Density Wave Instabilities in Steam Generators 201
Scaling of complex phenomena in System Thermalhydraulics 201
Capabilities of Transuranus Code in Simulating Power Ramp Tests from the IFPE Database 201
Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code 201
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures 200
FONESYS : The Forum & Network of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics 200
Evaluation of uncertainties in system thermal-hydraulic calculations and key applications by the CIAU method 199
Effect of Steam Generator Heat Transfer upon Core Reflood in a PWR 198
RBMK Fuel Channel Blockage Reactivity Analysis by MCNP5 and RELAP5-3D© codes 198
Validation of Neptune CFD Module With Data of a Plunging Water Jet Entering a Free Surface 198
Proposed Set of Criteria in Designing Nuclear Power Plants Experimental Simulators 197
Assessment study of the coupled code Relap5/Parcs against the Peach Bottom BWR turbine trip test 197
Overview of accident analysis in nuclear research reactors 197
Totale 30.440
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Categoria #
all - tutte 447.300
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 447.300
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/202212.952 0 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
2024/202532.983 498 1.742 605 1.687 1.446 1.751 2.694 2.387 4.231 5.045 4.441 6.456
2025/202640.072 1.906 6.091 4.943 4.867 3.042 3.924 5.190 2.007 2.452 3.188 1.810 652
2026/20274.214 1.411 2.803 0 0 0 0 0 0 0 0 0 0
Totale 173.380