CINECA IRIS Institutional Research Information System

ORIOLO, FRANCESCO
 Distribuzione geografica
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Continente #
NA - Nord America 7.225
EU - Europa 3.387
AS - Asia 1.732
AF - Africa 81
OC - Oceania 52
Continente sconosciuto - Info sul continente non disponibili 9
SA - Sud America 7
Totale 12.493
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Nazione #
US - Stati Uniti d'America 6.900
IT - Italia 973
CN - Cina 916
DE - Germania 598
SE - Svezia 593
BG - Bulgaria 433
CA - Canada 317
SG - Singapore 276
UA - Ucraina 222
FI - Finlandia 173
TR - Turchia 160
VN - Vietnam 160
GB - Regno Unito 121
RU - Federazione Russa 79
CH - Svizzera 67
HK - Hong Kong 63
AU - Australia 51
KR - Corea 49
CI - Costa d'Avorio 43
IN - India 40
FR - Francia 39
BE - Belgio 34
JP - Giappone 22
NG - Nigeria 21
PL - Polonia 20
IR - Iran 14
ID - Indonesia 13
BJ - Benin 10
EU - Europa 9
MX - Messico 8
NL - Olanda 7
RO - Romania 6
TH - Thailandia 6
IE - Irlanda 5
CZ - Repubblica Ceca 4
TW - Taiwan 4
BR - Brasile 3
CO - Colombia 3
HR - Croazia 3
MA - Marocco 3
AT - Austria 2
DZ - Algeria 2
ES - Italia 2
GE - Georgia 2
PK - Pakistan 2
AZ - Azerbaigian 1
BD - Bangladesh 1
BY - Bielorussia 1
GR - Grecia 1
HU - Ungheria 1
IL - Israele 1
JO - Giordania 1
KE - Kenya 1
MD - Moldavia 1
MT - Malta 1
MY - Malesia 1
NZ - Nuova Zelanda 1
PE - Perù 1
SI - Slovenia 1
SN - Senegal 1
Totale 12.493
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Città #
Woodbridge 1.112
Ann Arbor 910
Chandler 785
Houston 671
Sofia 433
Fairfield 340
Beijing 305
Ottawa 295
Jacksonville 279
Milan 269
New York 240
Ashburn 238
Serra 206
Boardman 173
Lawrence 164
Princeton 164
Nanjing 155
Wilmington 147
Izmir 146
Seattle 136
Singapore 131
Medford 126
Des Moines 125
Cambridge 112
Bern 64
Dearborn 59
Nanchang 58
Dong Ket 57
Redwood City 56
Frankfurt am Main 54
Brisbane 48
Hong Kong 48
Kunming 47
Abidjan 43
Jüchen 43
Shanghai 38
Ogden 34
Rome 30
Changsha 29
Shenyang 29
Hefei 27
Guangzhou 23
Hangzhou 23
Brussels 22
Falls Church 22
Hebei 21
Lagos 21
San Diego 21
Xian 20
Washington 19
Tianjin 18
Orange 17
Auburn Hills 16
Boulder 16
Jiaxing 16
Warsaw 16
Norwalk 15
Pusan 15
Pisa 14
Seoul 14
Gurgaon 13
Pune 12
Nürnberg 11
Cotonou 10
London 10
Tokyo 10
Changchun 9
Jakarta 9
Isfahan 8
Los Angeles 8
Verona 8
Cuauhtémoc 7
Rensselaer 7
Shatin 7
Düsseldorf 6
Lanzhou 6
Toronto 6
Zhengzhou 6
Central 5
Dublin 5
Florence 5
Jinan 5
Kocaeli 5
Sherbrooke 5
Alessandria 4
Dallas 4
Duncan 4
Harbin 4
Ningbo 4
South Milwaukee 4
Walnut 4
Albuquerque 3
Benton Harbor 3
Birmingham 3
Chongqing 3
Gif-sur-yvette 3
Ibra 3
Khorasan 3
Livorno 3
Modena 3
Totale 9.013
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Nome #
Experiments and CFD Analyses on Condensation Heat Transfer on a Flat Plate in a Square Cross Section Channel 337
Nuclear fission energy as a long term alternative to fossil fuels 213
Thermal-hydraulic Analysis of the LACE Experiments and its fall-out on the Safety Analysis of LWRs containment systems 178
Heavy liquid metal natural circulation in a one-dimensional loop 161
Heat Transfer from a Plate Cooled by a Water Film with Counter-Current Air Flow 158
Experimental and computational investigation of LBE–water interaction in LIFUS 5 facility 152
Principi di Ingegneria Nucleare - Generazione e trasporto del calore 146
Comparison and Analysis of the Condensation Benchmark Results 139
A one-dimensional coarse-mesh method for conduction in heat structures 136
Scaling Analysis for APWR Concrete Containment Passive Cooling System 131
FASTRAP: a very fast-running code for the analysis of Special Transients and SB-LOCAs in PWRs 117
A model for simulating natural circulation phenomena in LWR containment system 116
AP-600 thermalhydraulic phenomenology: a RELAP5/MOD2 model simulation 114
Realistic Evaluation of the Safety Margins in Nuclear Containment Systems 114
Modelling of Heat Transfer from a Falling Film in the Presence of Interfacial Shear 111
Preliminary Safety Analysis of the IRIS Reactor 109
Eletricity generation system for a sustainable development 108
An Integrated Approach to the Hydrogen Challenge in the Containment System of Advanced LWRs 107
M. Bucci, W. Ambrosini, N. Forgione, F. Oriolo, S. Paci 106
Natural Circulation Of Lead-bismuth In A One-dimensional Loop: Experiments And Code Predictions 106
A new integrated containment system for PWRs, able to mitigate severe accidents 106
Heat and Mass Transfer Models in LWRs Containment Systems 105
Comparison and Analysis of the Condensation Benchmark Results 105
An integrated model for evaluating the thermal-hydraulic behaviour of primary system and containment in innovative LWRs 104
Experimental study on combined natural and gas-injection enhanced circulation 104
Evaluation of Containment Heat and Mass Transfer Models with Consideration on the PHEBUS-FP Containment Vessel 104
Realistic simulation of Thermalhydraulic transients in full pressure containment system during severe accidents 103
The Safety Margins Evaluation in Next Generation of Nuclear Reactors 102
Experimental Study on Gas-Injection Enhanced Circulation performed with the CIRCE Facility 101
Thermal-Hydraulic Modelling in Support to Severe Accident Radionuclide Transport 99
Experimental Study on Natural Circulation and Air-Injection Enhanced Circulation With Different Fluids 99
Code accuracy evaluation of ISP 35 calculations based on NUPEC M-7-1 test 99
IRIS – an Advanced, Grid-Appropriate PWR for Near-Term Deployment 97
Validation of the ARIANNA-2 code on the basis of the HDR V44 and T31.5 Tests 96
Experimental Investigation on Wave Velocity in a Falling Film 96
On Various Forms of the Heat and Mass Transfer Analogy: Discussion and Application to Condensation Experiments 95
Scaling of Containment Experiments 95
An Integrated Approach to the Hydrogen Challenge in the Containment System of Advanced LWRs 94
The Coupled Phenomenology of Accident Evolution for Primary System and Containment in Innovative LWRs 92
Experimental study on combined natural and gas-injection enhanced circulation 92
Falling Film Evaporation In A Rectangular Channel With Different Depth 92
Modelling Requirements for Source Term Evaluation in Simplified LWRs 91
Oxidation Phenomena in Severe Accident (OPSA) 89
Experimental Data Base for Containment Thermal-Hydraulic Analysis 89
Challenges to Computing Buoyancy-Driven Flows in the Containment System of LWRs 88
Discussion of Heat and Mass Transfer Models on the Basis of Experiments and CFD Calculations 88
Testing and qualification of CIRCE instrumentation based on bubble tubes 88
The Problem of the Thermal-hydraulic Transient Inside Full Pressure Containment System Following a LOCA 88
An Integrated Approach between Primary System and Containment to Evaluate the Source Term in Advanced LWRs 87
Heat transfer from a plate cooled by a water film with counter-current air flow 86
An Integrated Approach between Primary System and Containment to Evaluate the Source Term in Advanced LWRs 86
SBWR Thermalhydraulic Performance: a RELAP5/MOD2 Model Simulation 85
Relevant Thermalhydraulic Aspects of New generation LWR's 85
Benchmarking Release, Circuit and Containment Codes against Phebus FP (PHEBEN) 84
Experimental Research on Containment Cooling by Evaporation of a Falling Film 84
Design of a Four Year Straight-Burn Core for the Generation IV IRIS Reactor 84
Experimental Investigation on Natural and Gas-injection Enhanced Circulation 84
Validation of the FUMO Code for the Analysis of Gas Distribution Phenomena in a LWR Containment System 83
Development and qualification of FUMO code for the containment system simulation of advanced LWRs 83
Application of Fractional Scaling Analysis for development and design of Integral Effects Test facility 83
Un metodo coarse-mesh per il calcolo del calore scambiato per conduzione nelle strutture di un impianto nucleare ad acqua leggera 82
Prediction of Heat and Mass Transfer In Innovative Nuclear Reactors 81
The Coupled Phenomenology of Accident Evolution for Containment and Primary System in Innovative LWRs 80
CFD Analysis of Passive Containment, Cooling by Falling Film Evaporation 80
IRIS: An Integrated International Approach to Design Deploy a New Generation Reactor, IAEA 80
Air Ingress Distribution and Source Term Evaluation During Mid-Loop Accident Sequences 80
Evaluation of Heat and Mass Transfer Models in LWRs Containment Systems 80
Experience in the Assessment of SCDAP/RELAP5 Computer Code 78
Prediction of Condensation Heat Transfer in LWRs Containment System 78
Investigation on Gas Distribution Phenomena inside the Containment System of LWRs 77
Evaluation of the Thermal-Hydraulic Phenomena in Generation IV Nuclear Power Plants 75
Development of a Coupled Containment-Reactor Coolant System Methodology for the Analysis of IRIS Small Break LOCA 75
HDR-CONT-STEAM Test V44: pre & post-test calculations using ARIANNA and CONTEMPT-LT/26 computer codes 75
Experimental Study on Natural Circulation and Air-Injection Enhanced Circulation with Different Fluids 74
Surface Characteristics of a Water Film Falling down a Flat Plate in the Laminar-Wavy 74
Physical phenomena relative to ex-vessel severe accident thermal-hydraulics in Italian LWR's containment systems 74
In-Vessel Core retention Strategy (IVCRS) 73
The Integrated Approach to the Accident Evaluation for Advanced LWRs - AP600 & SBWR Plants 73
Experimental Data Base for Containment Thermalhydraulic Analysis 72
Steam Condensation in the Presence of Air: Prediction of Test Conditions by One-Dimensional and CFD Codes 72
Integrated Thermal-Hydraulic and Aerosol Analysis of the VANAM M3 Test Using the ECART Code 72
Calculation of the thermal-hydraulic transient in multicompartment system by ARIANNA computer codes 72
-Hydraulic modelling in support to severe accident radionuclide transport 71
Validation of the FUMO Code for the Analysis of Gas Distribution Phenomena in a LWR Containment System 71
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 71
The Coupled Phenomenology of Accident Evolution for Containment and Primary System in Innovative LWRs 70
CFD Analysis of Air Ingress Distribution During Mid-Loop Accident Sequences 69
Core coolability and corium retention in a LWR 69
The Coupled Phenomenology of Accident Evolution for Containment and Primary System in Innovative LWRs 68
Progressi tecnologici dell'Energia Nucleare: Scorie e non Proliferazione 68
Statistical Characteristics of a Water Film Falling Down a Flat Plate at Different Inclinations and Temperatures 68
Prediction of Condensation in a Prototypical Passive Containment Condenser 68
Themal-Hydraulic modelling in support to severe accident radionuclide transport 67
Validation of a CFD Condensation Model Based on Heat and Mass Transfer Analogy by TOSQAN Facility ISP47 Test 67
Prediction of transpiration effects on heat and mass transfer by different turbulence models 66
Experiments and Modelling Techniques for Heat and Mass Transfer in Light Water Reactors 66
Investigation of Core Degradation (COBE) 64
Il funzionamento delle salvaguardie ingegneristiche di un sistema di contenimento a piena pressione in caso d'incidente severo 64
MELCOR 1.8.5 Analysis for the Phases II & III of the PHEBUS Test FPT-1 63
Evaluation of Heat and Mass Transfer Models in LWRs Containment Systems , , vol. CD , pp. CD -, San Francisco (USA) 1999 63
Totale 9.464
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Categoria #
all - tutte 31.323
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 31.323
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/2020958 0 0 0 66 128 130 166 67 128 108 145 20
2020/20211.004 79 34 77 31 196 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
2024/2025361 28 192 73 68 0 0 0 0 0 0 0 0
Totale 12.622