CINECA IRIS Institutional Research Information System

LO FRANO, ROSA
 Distribuzione geografica
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Continente #
NA - Nord America 11.122
AS - Asia 5.373
EU - Europa 4.184
SA - Sud America 751
AF - Africa 168
OC - Oceania 12
Continente sconosciuto - Info sul continente non disponibili 8
AN - Antartide 1
Totale 21.619
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Nazione #
US - Stati Uniti d'America 10.876
IT - Italia 1.903
SG - Singapore 1.801
CN - Cina 1.645
HK - Hong Kong 970
BR - Brasile 640
SE - Svezia 443
DE - Germania 373
BG - Bulgaria 346
VN - Vietnam 335
FR - Francia 201
CA - Canada 193
FI - Finlandia 191
RU - Federazione Russa 189
GB - Regno Unito 153
KR - Corea 139
IN - India 88
UA - Ucraina 80
TR - Turchia 76
JP - Giappone 64
BD - Bangladesh 54
MA - Marocco 53
CH - Svizzera 50
AT - Austria 48
AR - Argentina 46
NL - Olanda 37
BE - Belgio 32
ID - Indonesia 32
MX - Messico 31
ZA - Sudafrica 30
ES - Italia 28
PL - Polonia 27
SA - Arabia Saudita 27
IE - Irlanda 25
IQ - Iraq 25
BJ - Benin 23
CI - Costa d'Avorio 18
EC - Ecuador 18
PK - Pakistan 15
UY - Uruguay 12
UZ - Uzbekistan 12
RO - Romania 11
IR - Iran 10
VE - Venezuela 10
CO - Colombia 9
TW - Taiwan 9
AU - Australia 8
NG - Nigeria 8
CZ - Repubblica Ceca 7
MY - Malesia 7
PH - Filippine 7
EG - Egitto 6
EU - Europa 6
IL - Israele 6
KE - Kenya 6
PE - Perù 6
LT - Lituania 5
NP - Nepal 5
RS - Serbia 5
TN - Tunisia 5
AE - Emirati Arabi Uniti 4
AM - Armenia 4
AZ - Azerbaigian 4
BY - Bielorussia 4
EE - Estonia 4
ET - Etiopia 4
HU - Ungheria 4
JM - Giamaica 4
KZ - Kazakistan 4
OM - Oman 4
PT - Portogallo 4
PY - Paraguay 4
AL - Albania 3
CL - Cile 3
CR - Costa Rica 3
GE - Georgia 3
GR - Grecia 3
KG - Kirghizistan 3
LK - Sri Lanka 3
SN - Senegal 3
TH - Thailandia 3
TT - Trinidad e Tobago 3
BB - Barbados 2
BS - Bahamas 2
CG - Congo 2
DK - Danimarca 2
DO - Repubblica Dominicana 2
HN - Honduras 2
JO - Giordania 2
LA - Repubblica Popolare Democratica del Laos 2
LB - Libano 2
NZ - Nuova Zelanda 2
PA - Panama 2
PS - Palestinian Territory 2
UG - Uganda 2
AQ - Antartide 1
BA - Bosnia-Erzegovina 1
BF - Burkina Faso 1
BN - Brunei Darussalam 1
BO - Bolivia 1
Totale 21.594
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Città #
Woodbridge 1.248
Ann Arbor 1.043
Ashburn 974
Hong Kong 950
Singapore 939
Houston 937
Fairfield 813
Santa Clara 730
Dallas 613
Chandler 541
Serra 408
Shanghai 370
Seattle 368
Sofia 346
Beijing 338
Wilmington 293
Cambridge 286
New York 272
Milan 221
Boardman 208
Hefei 163
Princeton 160
Ottawa 151
Los Angeles 150
Lawrence 149
Des Moines 143
Medford 117
Dong Ket 103
Seoul 100
Florence 93
Nanjing 87
Jacksonville 78
Munich 78
Pisa 78
Buffalo 69
Lucca 68
Frankfurt am Main 67
Redondo Beach 60
Rome 53
Dearborn 51
Helsinki 50
Ho Chi Minh City 47
São Paulo 47
Marseille 43
Casablanca 41
Vienna 40
Tokyo 39
Boulder 36
Hanoi 35
San Diego 34
Ogden 33
Redwood City 33
Bern 32
Turku 32
Kunming 30
San Vito Chietino 28
Columbus 27
London 27
Istanbul 26
Nanchang 26
The Dalles 26
Cotonou 23
Dublin 23
Falkenstein 23
Rio de Janeiro 23
Belo Horizonte 22
Brussels 22
Châteauneuf-le-rouge 22
Council Bluffs 22
Falls Church 22
Fuzhou 22
Guangzhou 21
Shenyang 21
Izmir 20
Chicago 19
Nuremberg 19
San Jose 19
Abidjan 18
Dhaka 18
Livorno 18
Riyadh 18
Tezze Sul Brenta 18
Salvador 17
San Francisco 17
Düsseldorf 16
Hebei 16
Norwalk 16
Quanzhou 16
Volterra 16
Carrara 15
Changsha 15
Johannesburg 15
Atlanta 14
Brooklyn 14
Chennai 14
Montreal 14
Warsaw 14
Ancona 13
Jiaxing 13
Mexico City 13
Totale 15.349
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Nome #
LFR safety approach and main ELFR safety analysis results 290
METHODOLOGY TO INVESTIGATE VIBRATION PHENOMENA CAUSED BY THE STEAM CONDENSATION AT SUB-ATMOSPHERIC CONDITION 263
Thermal Tests Of A CP5.2 Packaging System: Post Experimental Test Description 248
PRELIMINARY ASSESSMENT OF THE FLUID-STRUCTURE INTERACTION EFFECTS IN A GEN IV LMR 217
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 215
PRELIMINARY EVALUATION OF THE RELIABILITY OF GEN II OR III REACTORS IN BDBE CONDITIONS 209
ANALYSIS OF SEISMIC ISOLATION PROBLEMS OF NPP BUILDINGS 203
Mitigation of a Loss of Coolant Accident in ITER Vacuum Vessel by Means of Steam Pressure Suppression 201
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 201
Manufacturing challenges and required R&D on fusion pebbles bed material 183
Aircraft Impact onto an existing nuclear plant 182
Thermo-mechanical test rig for experimental evaluation of thermal conductivity of ceramic pebble beds 182
Application of PHADEC method for the decontamination of radioactive steam piping components 179
Three-dimensional condensation regime diagram for direct contact condensation of steam injected into water at subatmospheric conditions 179
Analysis of vibrations due to the steam condensation at sub-atmospheric condition 179
Analysis of the effects caused by the core compaction into LFR reactor 177
PRELIMINARY EVALUATION OF CORE COMPACTION PHENOMENON: METHODOLOGICAL APPROACH 176
THERMAL TESTS OF A CP5.2 PACKAGING SYSTEM: PROTOTYPE AND EXPERIMENTAL TEST DESCRIPTION 176
Application of PHADEC method for the decontamination of radioactive steam piping components of Caorso plant 166
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 165
Experimental investigation of functional performance of a vacuum vessel pressure suppression system of ITER 164
CHARACTERIZATION OF FUTURIX-FTA IRRADIATED NUCLEAR FUEL SAMPLES 162
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 159
Analysis of hydrogen deflagration/detonation effects in vacuum pressure suppression tank 159
Investigation of liquid metal embrittlement of AISI 316L steels 158
Experimental analysis of steam condensation patterns within a pressure suppression system operating at sub-atmospheric pressure conditions 158
Preliminary evaluation of the seismic response of the ELSY LFR 156
Demonstration of structural performance of IP-2 package by simulation and full-scale horizontal free drop test 156
Experimental investigation of steam condensation in water tank at sub-atmospheric pressure 156
Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials 155
Preliminary evaluation of aircraft impact on a near term nuclear power plant 155
Buckling of thin cylindrical shell subject to uniform external pressure 153
Investigation of vibrations caused by the steam condensation at sub-atmospheric condition in VVPSS 153
Evaluation of safety performances of a superficial disposal facility subject to an aircraft impact and fuel burning 152
Thermal tests of a CP5.2 packaging system: Prototype and experimental test description 152
CFD thermal analysis of ITER pressure suppression tanks 152
Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials 151
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 150
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 150
Dismantling of the graphite pile of Latina NPP: Characterization and handling/removal equipment for single brick or multi-bricks 149
Handling and conditioning techniques of activated chips for the decommissioning of the E. Fermi nuclear power plant 149
Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket 148
Preliminary evaluation of the safety margin of a Gen II reactor subjected to an aircraft impact 147
Preliminary Analysis of Creep and Ageing Influence During SBO 146
Evaluation of damaging effects on a NPP integrity subjected to beyond design earthquake 145
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 144
Conceptual evaluation of fluid-structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor 144
Influence of the curved geometrical shape on the thin shell buckling phenomenon behaviour 144
Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket 144
Manufacturing technology of ceramic pebbles for breeding blanket 144
null 143
Experimental thermal characterization of concrete to be used in CP5.2 packaging system 143
Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor 143
Integrity of pressure vessel lower head in case of corium relocation: identification of loads and failure modes 143
Preliminary evaluation of structural response of ELSY reactor in the after shutdown condition 142
Horizontal drop test evaluation of a packaging system 142
Analysis Of The Core Compaction Phenomenon 142
Feasibility study of a new fabrication method for the Li4Sio4 pebbles 142
Seismic analysis approach applied to a small size next generation nuclear reactor 139
Thermal analysis of a spent fuel cask in different transport conditions 138
null 138
Rigorous Dynamic Simulation of Cryogenic Distillation of Hydrogen Isotopologues in the Fuel Cycle of a Thermonuclear Reactor Based on UV Flash 138
Feasibility study of desalination plant powered by SMR 137
Thermodynamics of the Lithium Loop in a Liquid Metal Divertor for Future Fusion Reactors 137
Thermal tests of a scaled down mock-up of CP5.2 packaging system: Post-test analysis 137
Direct condensation of steam in a water tank at subatmospheric Pressures’ 137
An improved substructuring approach for dynamic modelling – The example of the ITER vacuum vessel 137
Influence of aircraft impact on seismic isolated SMR reactor 135
GLOBAL STRUCTURAL RESPONSE OF AN SMR REACTOR SUBJECTED TO AN AIRCRAFT IMPACT 134
Lithium orthosilicate as nuclear fusion breeder material: Optimization of the drip casting production technology 133
Investigation on thermal treatments of high-resistance austenitic stainless steels employed as structural materials in generation IV reactors 132
ORIGINAL CORE CATCHER DESIGN IN ORDER TO MANAGE THE CORE MELTDOWN SEVERE ACCIDENT WITH THE IN-VESSEL RETENTION STRATEGY 132
Experimental thermal characterization of concrete to be used in CP5.2 packaging system 132
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 131
SEISMIC SAFETY MARGIN OF AN ISOLATED SMR REACTOR UNDER SEVERE EARTHQUAKE 131
Preliminary Evaluation of Aircraft Impact on a Near Term Nuclear Power Plant 129
Isolation systems influence in the seismic loading propagation analysis applied to an innovative near term reactor 129
Thermo-mechanical characterization of ceramic pebbles for breeding blanket 129
Preliminary evaluation of the flooding effects on an existing PWR 128
Seismic response of reactor vessel internals in the IRIS reactor 126
EVALUATION OF THE ISOLATION SYSTEM INFLUENCE IN THE SEISMIC LOADING ANALISYS APPLIED TO A NEAR TERM DEPLOYMENT REACTOR 125
External Event Risk Assessment: Methodology and Application 124
Structural performance of an IP2 package in free drop test conditions: numerical and experimental evaluations 123
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 123
Computational fluid dynamics thermal analysis of ITER pressure suppression tanks 123
Post-test of the sgtr experimental tests carried out in the LIFUS facility 122
EM zooming procedure in ANSYS Maxwell 3D 122
Safety performance of a near surface repository subject to a fuel burning 121
Fluid dynamics analysis of loss of vacuum accident of ITER cryostat 121
Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant 121
Numerical and experimental evaluations of the effects of a packaging system free drop 120
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 119
Performances of the ITER Pressure Suppression System during unstable steam condensation regimes 118
Buckling of imperfect cylindrical shell under lateral pressure 118
Simplified Models of the ITER Vacuum Vessel for Global Seismic Analyses 118
Enhanced radioactive waste drum monitoring: A sensorized LoRa-based network for identification and integrity assessment 117
Design methodology of multi-hole spargers to prevent steam coalescence at sub-atmospheric pressure 116
Preliminary evaluation of a severe flooding effects on an innovative SMR 114
Earthquake response analysis of reactor vessel internals for next generation reactors 114
Evaluation Of Instability Of Laminated Rubber Bearings Under Dynamic Loading 113
Totale 15.017
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Categoria #
all - tutte 68.167
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 68.167
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021798 0 0 0 0 0 53 86 108 117 137 89 208
2021/20221.646 25 106 41 82 257 230 85 71 102 135 81 431
2022/20231.778 206 149 130 124 207 298 11 122 346 22 143 20
2023/20241.545 185 129 241 71 201 239 125 55 32 36 65 166
2024/20255.308 53 226 81 252 496 564 485 298 526 729 601 997
2025/20263.522 308 761 736 526 660 531 0 0 0 0 0 0
Totale 21.975