CINECA IRIS Institutional Research Information System

ORIOLO, FRANCESCO
 Distribuzione geografica
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Continente #
NA - Nord America 9.159
AS - Asia 5.260
EU - Europa 3.732
SA - Sud America 624
AF - Africa 142
OC - Oceania 141
Continente sconosciuto - Info sul continente non disponibili 11
Totale 19.069
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Nazione #
US - Stati Uniti d'America 8.771
CN - Cina 2.140
SG - Singapore 1.223
IT - Italia 982
HK - Hong Kong 917
DE - Germania 635
SE - Svezia 599
BR - Brasile 542
BG - Bulgaria 435
CA - Canada 337
TR - Turchia 238
UA - Ucraina 231
KR - Corea 228
RU - Federazione Russa 215
VN - Vietnam 212
FI - Finlandia 202
GB - Regno Unito 159
AU - Australia 140
CH - Svizzera 74
IN - India 71
FR - Francia 59
CI - Costa d'Avorio 43
BE - Belgio 39
JP - Giappone 36
BD - Bangladesh 33
AR - Argentina 28
PL - Polonia 24
IQ - Iraq 22
MX - Messico 21
NG - Nigeria 21
ID - Indonesia 20
ZA - Sudafrica 17
JO - Giordania 16
VE - Venezuela 16
NL - Olanda 15
SA - Arabia Saudita 15
IR - Iran 14
MA - Marocco 14
PK - Pakistan 14
BJ - Benin 10
CO - Colombia 10
EC - Ecuador 9
EU - Europa 9
KE - Kenya 9
UZ - Uzbekistan 9
ES - Italia 8
EG - Egitto 7
IE - Irlanda 7
IL - Israele 7
NP - Nepal 7
PE - Perù 7
PY - Paraguay 7
RO - Romania 7
TN - Tunisia 7
CZ - Repubblica Ceca 6
GR - Grecia 6
TH - Thailandia 6
AT - Austria 5
PA - Panama 5
AZ - Azerbaigian 4
BB - Barbados 4
NO - Norvegia 4
PH - Filippine 4
SI - Slovenia 4
TT - Trinidad e Tobago 4
TW - Taiwan 4
HR - Croazia 3
MD - Moldavia 3
OM - Oman 3
AE - Emirati Arabi Uniti 2
AL - Albania 2
AO - Angola 2
CR - Costa Rica 2
DZ - Algeria 2
ET - Etiopia 2
GE - Georgia 2
GT - Guatemala 2
HU - Ungheria 2
JM - Giamaica 2
KW - Kuwait 2
KY - Cayman, isole 2
LB - Libano 2
MY - Malesia 2
MZ - Mozambico 2
UY - Uruguay 2
XK - ???statistics.table.value.countryCode.XK??? 2
AG - Antigua e Barbuda 1
AM - Armenia 1
BA - Bosnia-Erzegovina 1
BY - Bielorussia 1
CL - Cile 1
DO - Repubblica Dominicana 1
GD - Grenada 1
GY - Guiana 1
HN - Honduras 1
JE - Jersey 1
KG - Kirghizistan 1
KZ - Kazakistan 1
LA - Repubblica Popolare Democratica del Laos 1
LC - Santa Lucia 1
Totale 19.051
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Città #
Woodbridge 1.112
Ann Arbor 910
Hong Kong 896
Ashburn 797
Chandler 785
Singapore 746
Houston 672
Shanghai 660
Santa Clara 578
Sofia 434
Beijing 373
Dallas 340
Fairfield 340
Ottawa 296
Jacksonville 281
Milan 269
New York 248
Hefei 238
Serra 207
Seoul 188
Boardman 173
Lawrence 164
Princeton 164
Nanjing 157
Wilmington 148
Izmir 146
Seattle 137
Medford 126
Des Moines 125
Cambridge 113
Brisbane 101
Los Angeles 77
Bern 64
Istanbul 63
Buffalo 60
Frankfurt am Main 60
Dearborn 59
Nanchang 58
Dong Ket 57
Redwood City 56
Redondo Beach 53
Kunming 49
Abidjan 43
Jüchen 43
São Paulo 42
Changsha 36
Ogden 34
Rome 31
Council Bluffs 30
Shenyang 30
Guangzhou 29
Brussels 27
Helsinki 25
Hangzhou 23
Falls Church 22
San Diego 22
Hebei 21
Lagos 21
Sydney 21
Washington 21
Ho Chi Minh City 20
Warsaw 20
Xian 20
Rio de Janeiro 19
Tianjin 19
Boulder 18
Orange 17
Tokyo 17
Auburn Hills 16
Jiaxing 16
Munich 16
Pisa 16
Amman 15
Norwalk 15
Pusan 15
Belo Horizonte 14
Düsseldorf 14
The Dalles 14
Columbus 13
Dhaka 13
Gurgaon 13
London 13
Pune 13
Baghdad 12
Fuzhou 12
Nürnberg 11
Cotonou 10
Jakarta 10
Toronto 10
Changchun 9
Johannesburg 9
Las Vegas 9
Amsterdam 8
Goiânia 8
Isfahan 8
Riyadh 8
San Francisco 8
Tashkent 8
Verona 8
Chengdu 7
Totale 13.622
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Nome #
Nuclear fission energy as a long term alternative to fossil fuels 424
Experiments and CFD Analyses on Condensation Heat Transfer on a Flat Plate in a Square Cross Section Channel 404
Validation of the ARIANNA-2 code on the basis of the HDR V44 and T31.5 Tests 401
Thermal-hydraulic Analysis of the LACE Experiments and its fall-out on the Safety Analysis of LWRs containment systems 241
Heavy liquid metal natural circulation in a one-dimensional loop 215
Heat Transfer from a Plate Cooled by a Water Film with Counter-Current Air Flow 206
Experimental and computational investigation of LBE–water interaction in LIFUS 5 facility 199
Comparison and Analysis of the Condensation Benchmark Results 199
Air Ingress Distribution and Source Term Evaluation During Mid-Loop Accident Sequences 198
A one-dimensional coarse-mesh method for conduction in heat structures 192
Principi di Ingegneria Nucleare - Generazione e trasporto del calore 191
A model for simulating natural circulation phenomena in LWR containment system 177
FASTRAP: a very fast-running code for the analysis of Special Transients and SB-LOCAs in PWRs 173
Realistic simulation of Thermalhydraulic transients in full pressure containment system during severe accidents 162
Scaling Analysis for APWR Concrete Containment Passive Cooling System 160
AP-600 thermalhydraulic phenomenology: a RELAP5/MOD2 model simulation 159
Realistic Evaluation of the Safety Margins in Nuclear Containment Systems 159
An integrated model for evaluating the thermal-hydraulic behaviour of primary system and containment in innovative LWRs 155
Experimental Study on Gas-Injection Enhanced Circulation performed with the CIRCE Facility 155
Preliminary Safety Analysis of the IRIS Reactor 152
Comparison and Analysis of the Condensation Benchmark Results 150
Thermal-Hydraulic Modelling in Support to Severe Accident Radionuclide Transport 149
IRIS – an Advanced, Grid-Appropriate PWR for Near-Term Deployment 148
The Safety Margins Evaluation in Next Generation of Nuclear Reactors 145
Eletricity generation system for a sustainable development 144
M. Bucci, W. Ambrosini, N. Forgione, F. Oriolo, S. Paci 144
Modelling of Heat Transfer from a Falling Film in the Presence of Interfacial Shear 144
Application of Fractional Scaling Analysis for development and design of Integral Effects Test facility 144
Experimental Study on Natural Circulation and Air-Injection Enhanced Circulation With Different Fluids 143
Discussion of Heat and Mass Transfer Models on the Basis of Experiments and CFD Calculations 142
Challenges to Computing Buoyancy-Driven Flows in the Containment System of LWRs 141
Natural Circulation Of Lead-bismuth In A One-dimensional Loop: Experiments And Code Predictions 141
Heat transfer from a plate cooled by a water film with counter-current air flow 140
-Hydraulic modelling in support to severe accident radionuclide transport 140
Heat and Mass Transfer Models in LWRs Containment Systems 140
Code accuracy evaluation of ISP 35 calculations based on NUPEC M-7-1 test 140
Experimental study on combined natural and gas-injection enhanced circulation 139
Evaluation of Containment Heat and Mass Transfer Models with Consideration on the PHEBUS-FP Containment Vessel 139
On Various Forms of the Heat and Mass Transfer Analogy: Discussion and Application to Condensation Experiments 138
A new integrated containment system for PWRs, able to mitigate severe accidents 138
Un metodo coarse-mesh per il calcolo del calore scambiato per conduzione nelle strutture di un impianto nucleare ad acqua leggera 137
An Integrated Approach to the Hydrogen Challenge in the Containment System of Advanced LWRs 136
The Coupled Phenomenology of Accident Evolution for Primary System and Containment in Innovative LWRs 135
CFD Analysis of Air Ingress Distribution During Mid-Loop Accident Sequences 135
Experimental study on combined natural and gas-injection enhanced circulation 134
Relevant Thermalhydraulic Aspects of New generation LWR's 134
Experience in the Assessment of SCDAP/RELAP5 Computer Code 133
Experimental Investigation on Wave Velocity in a Falling Film 132
Validation of the FUMO Code for the Analysis of Gas Distribution Phenomena in a LWR Containment System 129
The Coupled Phenomenology of Accident Evolution for Containment and Primary System in Innovative LWRs 129
An Integrated Approach to the Hydrogen Challenge in the Containment System of Advanced LWRs 129
Modelling Requirements for Source Term Evaluation in Simplified LWRs 129
Experimental Research on Containment Cooling by Evaporation of a Falling Film 126
An Integrated Approach between Primary System and Containment to Evaluate the Source Term in Advanced LWRs 125
Scaling of Containment Experiments 125
Investigation on Gas Distribution Phenomena inside the Containment System of LWRs 123
CFD Analysis of Passive Containment, Cooling by Falling Film Evaporation 123
Testing and qualification of CIRCE instrumentation based on bubble tubes 123
Characterization of a Falling Film for Heat and Mass Transfer Experiments 121
Falling Film Evaporation In A Rectangular Channel With Different Depth 121
The Problem of the Thermal-hydraulic Transient Inside Full Pressure Containment System Following a LOCA 121
The Integrated Approach to the Accident Evaluation for Advanced LWRs - AP600 & SBWR Plants 120
IRIS: An Integrated International Approach to Design Deploy a New Generation Reactor, IAEA 119
Oxidation Phenomena in Severe Accident (OPSA) 119
An Integrated Approach between Primary System and Containment to Evaluate the Source Term in Advanced LWRs 119
Benchmarking Release, Circuit and Containment Codes against Phebus FP (PHEBEN) 118
Prediction of Heat and Mass Transfer In Innovative Nuclear Reactors 118
Experimental Study on Natural Circulation and Air-Injection Enhanced Circulation with Different Fluids 118
Prediction of transpiration effects on heat and mass transfer by different turbulence models 117
Experimental Investigation on Natural and Gas-injection Enhanced Circulation 117
SBWR Thermalhydraulic Performance: a RELAP5/MOD2 Model Simulation 117
Surface Characteristics of a Water Film Falling down a Flat Plate in the Laminar-Wavy 116
The Coupled Phenomenology of Accident Evolution for Containment and Primary System in Innovative LWRs 115
Design of a Four Year Straight-Burn Core for the Generation IV IRIS Reactor 115
Development and qualification of FUMO code for the containment system simulation of advanced LWRs 115
Core coolability and corium retention in a LWR 114
Evaluation of Heat and Mass Transfer Models in LWRs Containment Systems 114
Experimental Data Base for Containment Thermal-Hydraulic Analysis 114
Prediction of Condensation Heat Transfer in LWRs Containment System 113
Steam Condensation in the Presence of Air: Prediction of Test Conditions by One-Dimensional and CFD Codes 111
LBE–water interaction in sub-critical reactors: First experimental and modelling results 110
Una proposta per la determinazione del coefficiente di scambio termico in sistemi di contenimento di reattori nucleari a seguito di incidente di perdita di refrigerante 110
HDR-CONT-STEAM Test V44: pre & post-test calculations using ARIANNA and CONTEMPT-LT/26 computer codes 110
CFD Analysis of Evaporation Cooling Experimental Tests 109
Experiments and Modelling Techniques for Heat and Mass Transfer in Light Water Reactors 108
The Coupled Phenomenology of Accident Evolution for Containment and Primary System in Innovative LWRs 107
Evaluation of the Thermal-Hydraulic Phenomena in Generation IV Nuclear Power Plants 106
Measurement of Falling Film Thickness by Capacitive Sensors 106
Development of a Coupled Containment-Reactor Coolant System Methodology for the Analysis of IRIS Small Break LOCA 106
Validation of the FUMO Code for the Analysis of Gas Distribution Phenomena in a LWR Containment System 106
Physical phenomena relative to ex-vessel severe accident thermal-hydraulics in Italian LWR's containment systems 106
Calculation of the thermal-hydraulic transient in multicompartment system by ARIANNA computer codes 106
Themal-Hydraulic modelling in support to severe accident radionuclide transport 103
Experimental Data Base for Containment Thermalhydraulic Analysis 103
In-Vessel Core retention Strategy (IVCRS) 101
Statistical Characteristics of a Water Film Falling Down a Flat Plate at Different Inclinations and Temperatures 101
Il funzionamento delle salvaguardie ingegneristiche di un sistema di contenimento a piena pressione in caso d'incidente severo 101
Experimental Investigation on Mixing Phenomena inside a Concrete Containment Cooled by a Innovative Passive System 100
Progressi tecnologici dell'Energia Nucleare: Scorie e non Proliferazione 99
Prediction of Condensation in a Prototypical Passive Containment Condenser 99
Totale 14.177
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Categoria #
all - tutte 49.300
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 49.300
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021587 0 0 0 0 0 43 75 109 60 54 63 183
2021/20221.558 11 164 47 84 340 198 34 58 64 28 47 483
2022/20231.911 237 195 144 178 249 286 11 146 343 14 78 30
2023/20241.414 164 146 187 76 217 274 75 32 26 28 43 146
2024/20254.880 28 192 73 241 458 393 654 301 492 635 505 908
2025/20262.057 167 637 420 282 395 156 0 0 0 0 0 0
Totale 19.198