CINECA IRIS Institutional Research Information System

LO FRANO, ROSA
 Distribuzione geografica
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Continente #
NA - Nord America 8.110
EU - Europa 3.254
AS - Asia 1.196
AF - Africa 27
SA - Sud America 16
Continente sconosciuto - Info sul continente non disponibili 6
OC - Oceania 6
Totale 12.615
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Nazione #
US - Stati Uniti d'America 7.948
IT - Italia 1.641
CN - Cina 596
SE - Svezia 431
BG - Bulgaria 346
SG - Singapore 217
DE - Germania 211
VN - Vietnam 179
CA - Canada 159
FR - Francia 133
FI - Finlandia 107
GB - Regno Unito 80
UA - Ucraina 69
RU - Federazione Russa 54
CH - Svizzera 47
HK - Hong Kong 40
KR - Corea 38
IN - India 35
TR - Turchia 35
AT - Austria 29
BE - Belgio 21
JP - Giappone 21
NL - Olanda 20
CI - Costa d'Avorio 18
ES - Italia 13
BR - Brasile 12
IE - Irlanda 12
PL - Polonia 12
RO - Romania 9
EU - Europa 6
NG - Nigeria 6
TW - Taiwan 6
AU - Australia 5
IR - Iran 5
CZ - Repubblica Ceca 4
ID - Indonesia 4
SA - Arabia Saudita 4
AE - Emirati Arabi Uniti 3
HU - Ungheria 3
KZ - Kazakistan 3
MY - Malesia 2
PK - Pakistan 2
PT - Portogallo 2
RS - Serbia 2
BD - Bangladesh 1
BN - Brunei Darussalam 1
BS - Bahamas 1
BY - Bielorussia 1
CL - Cile 1
DK - Danimarca 1
DO - Repubblica Dominicana 1
EC - Ecuador 1
EE - Estonia 1
FK - Isole Falkland (Malvinas) 1
GH - Ghana 1
GR - Grecia 1
JO - Giordania 1
LA - Repubblica Popolare Democratica del Laos 1
LT - Lituania 1
LU - Lussemburgo 1
MK - Macedonia 1
MP - Marianne Settentrionali, isole 1
MX - Messico 1
NO - Norvegia 1
PE - Perù 1
PH - Filippine 1
SL - Sierra Leone 1
TH - Thailandia 1
ZA - Sudafrica 1
Totale 12.615
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Città #
Woodbridge 1.248
Ann Arbor 1.043
Houston 932
Fairfield 813
Chandler 541
Serra 407
Seattle 367
Ashburn 363
Sofia 346
Wilmington 293
Cambridge 286
New York 245
Beijing 238
Milan 200
Princeton 160
Lawrence 149
Ottawa 147
Des Moines 143
Medford 117
Dong Ket 103
Nanjing 86
Florence 80
Jacksonville 76
Dearborn 51
Frankfurt am Main 50
Marseille 38
Boulder 36
Pisa 36
Rome 34
San Diego 34
Redwood City 33
Bern 32
Hong Kong 30
Kunming 29
Vienna 29
San Vito Chietino 28
Los Angeles 27
Nanchang 26
Singapore 25
Boardman 24
Châteauneuf-le-rouge 22
Falls Church 22
Shenyang 19
Abidjan 18
Izmir 18
Tezze Sul Brenta 18
Hefei 17
Hebei 16
Norwalk 16
Volterra 16
Brussels 15
Carrara 15
Changsha 14
Jiaxing 13
Ogden 13
Kocaeli 12
Lucca 12
Livorno 11
Bremen 10
Dublin 10
Guangzhou 10
Hangzhou 10
Jüchen 10
London 10
Xian 10
Lanzhou 9
Osaka 9
San Francisco 9
Zhengzhou 9
Auburn Hills 8
Central 8
Nürnberg 8
Soverato 8
São Paulo 8
Tianjin 8
Tortona 8
Bologna 7
Karlsruhe 7
Lissone 7
Petten 7
Pian Camuno 7
Pontedera 7
Tappahannock 7
Bellante 6
Chicago 6
Chongqing 6
Gif-sur-yvette 6
Helsinki 6
Indiana 6
Lagos 6
Moscow 6
Tokyo 6
Washington 6
Dubna 5
Genoa 5
Jinan 5
Manchester 5
Massa 5
Perugia 5
Rotterdam 5
Totale 9.538
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Nome #
METHODOLOGY TO INVESTIGATE VIBRATION PHENOMENA CAUSED BY THE STEAM CONDENSATION AT SUB-ATMOSPHERIC CONDITION 215
LFR safety approach and main ELFR safety analysis results 175
Thermal Tests Of A CP5.2 Packaging System: Post Experimental Test Description 165
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 150
null 143
Application of PHADEC method for the decontamination of radioactive steam piping components 141
PRELIMINARY ASSESSMENT OF THE FLUID-STRUCTURE INTERACTION EFFECTS IN A GEN IV LMR 140
Thermo-mechanical test rig for experimental evaluation of thermal conductivity of ceramic pebble beds 140
Analysis of the effects caused by the core compaction into LFR reactor 139
null 138
ANALYSIS OF SEISMIC ISOLATION PROBLEMS OF NPP BUILDINGS 136
Mitigation of a Loss of Coolant Accident in ITER Vacuum Vessel by Means of Steam Pressure Suppression 136
THERMAL TESTS OF A CP5.2 PACKAGING SYSTEM: PROTOTYPE AND EXPERIMENTAL TEST DESCRIPTION 135
PRELIMINARY EVALUATION OF THE RELIABILITY OF GEN II OR III REACTORS IN BDBE CONDITIONS 134
PRELIMINARY EVALUATION OF CORE COMPACTION PHENOMENON: METHODOLOGICAL APPROACH 133
Application of PHADEC method for the decontamination of radioactive steam piping components of Caorso plant 131
Manufacturing challenges and required R&D on fusion pebbles bed material 129
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 127
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 125
Aircraft Impact onto an existing nuclear plant 122
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 118
Three-dimensional condensation regime diagram for direct contact condensation of steam injected into water at subatmospheric conditions 116
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 115
Preliminary evaluation of aircraft impact on a near term nuclear power plant 112
Experimental thermal characterization of concrete to be used in CP5.2 packaging system 112
Analysis of vibrations due to the steam condensation at sub-atmospheric condition 112
Buckling of thin cylindrical shell subject to uniform external pressure 110
Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials 110
Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials 109
CHARACTERIZATION OF FUTURIX-FTA IRRADIATED NUCLEAR FUEL SAMPLES 109
Experimental investigation of functional performance of a vacuum vessel pressure suppression system of ITER 109
Seismic analysis approach applied to a small size next generation nuclear reactor 108
Experimental investigation of steam condensation in water tank at sub-atmospheric pressure 108
Influence of the curved geometrical shape on the thin shell buckling phenomenon behaviour 107
Investigation of liquid metal embrittlement of AISI 316L steels 106
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 105
Thermal tests of a CP5.2 packaging system: Prototype and experimental test description 105
Analysis of hydrogen deflagration/detonation effects in vacuum pressure suppression tank 105
Preliminary Analysis of Creep and Ageing Influence During SBO 105
Preliminary evaluation of the seismic response of the ELSY LFR 104
Manufacturing technology of ceramic pebbles for breeding blanket 103
Investigation of vibrations caused by the steam condensation at sub-atmospheric condition in VVPSS 103
Thermal analysis of a spent fuel cask in different transport conditions 102
CFD thermal analysis of ITER pressure suppression tanks 102
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 101
Evaluation of damaging effects on a NPP integrity subjected to beyond design earthquake 101
Evaluation of safety performances of a superficial disposal facility subject to an aircraft impact and fuel burning 101
Dismantling of the graphite pile of Latina NPP: Characterization and handling/removal equipment for single brick or multi-bricks 100
Experimental thermal characterization of concrete to be used in CP5.2 packaging system 100
Experimental analysis of steam condensation patterns within a pressure suppression system operating at sub-atmospheric pressure conditions 100
Structural performance of an IP2 package in free drop test conditions: numerical and experimental evaluations 98
SEISMIC SAFETY MARGIN OF AN ISOLATED SMR REACTOR UNDER SEVERE EARTHQUAKE 98
External Event Risk Assessment: Methodology and Application 97
Demonstration of structural performance of IP-2 package by simulation and full-scale horizontal free drop test 97
null 97
Handling and conditioning techniques of activated chips for the decommissioning of the E. Fermi nuclear power plant 96
Conceptual evaluation of fluid-structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor 95
Thermo-mechanical characterization of ceramic pebbles for breeding blanket 95
Investigation on thermal treatments of high-resistance austenitic stainless steels employed as structural materials in generation IV reactors 95
Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket 95
Thermal tests of a scaled down mock-up of CP5.2 packaging system: Post-test analysis 95
Feasibility study of a new fabrication method for the Li4Sio4 pebbles 95
null 94
Preliminary evaluation of the safety margin of a Gen II reactor subjected to an aircraft impact 93
GLOBAL STRUCTURAL RESPONSE OF AN SMR REACTOR SUBJECTED TO AN AIRCRAFT IMPACT 93
Rigorous Dynamic Simulation of Cryogenic Distillation of Hydrogen Isotopologues in the Fuel Cycle of a Thermonuclear Reactor Based on UV Flash 93
Integrity of pressure vessel lower head in case of corium relocation: identification of loads and failure modes 93
Preliminary Evaluation of Aircraft Impact on a Near Term Nuclear Power Plant 92
Isolation systems influence in the seismic loading propagation analysis applied to an innovative near term reactor 92
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 92
Analysis Of The Core Compaction Phenomenon 92
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 91
Fluid dynamics analysis of loss of vacuum accident of ITER cryostat 91
EVALUATION OF THE ISOLATION SYSTEM INFLUENCE IN THE SEISMIC LOADING ANALISYS APPLIED TO A NEAR TERM DEPLOYMENT REACTOR 89
Preliminary evaluation of structural response of ELSY reactor in the after shutdown condition 89
Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor 89
Horizontal drop test evaluation of a packaging system 86
An improved substructuring approach for dynamic modelling – The example of the ITER vacuum vessel 86
ORIGINAL CORE CATCHER DESIGN IN ORDER TO MANAGE THE CORE MELTDOWN SEVERE ACCIDENT WITH THE IN-VESSEL RETENTION STRATEGY 85
Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket 85
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 84
EM zooming procedure in ANSYS Maxwell 3D 83
Direct condensation of steam in a water tank at subatmospheric Pressures’ 82
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 81
Preliminary evaluation of the flooding effects on an existing PWR 80
Evaluation Of Instability Of Laminated Rubber Bearings Under Dynamic Loading 79
Influence of aircraft impact on seismic isolated SMR reactor 78
Investigation of the behaviour of a LILW superficial repository under aircraft impact 78
Thermodynamics of the Lithium Loop in a Liquid Metal Divertor for Future Fusion Reactors 76
Simplified models of the ITER vacuum vessel for global seismic analyses 76
Earthquake response analysis of reactor vessel internals for next generation reactors 74
Buckling of imperfect cylindrical shell under lateral pressure 74
Post-test of the sgtr experimental tests carried out in the LIFUS facility 74
Seismic response of reactor vessel internals in the IRIS reactor 73
Preliminary safety evaluation of an aircraft impact on a near-surface RWs repository 73
Buckling of thin cylindrical shell subject to uniform external pressure 72
Numerical and experimental evaluations of the effects of a packaging system free drop 72
Numerical analysis of steam condensation at sub-atmospheric pressure in water suppression tank 72
Simplified Models of the ITER Vacuum Vessel for Global Seismic Analyses 71
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 68
Totale 10.350
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Categoria #
all - tutte 38.251
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 38.251
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/2019610 0 0 0 0 0 0 0 0 0 144 247 219
2019/20202.036 233 144 152 140 187 208 240 185 208 121 175 43
2020/20211.260 76 45 73 44 224 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
2023/20241.314 185 129 241 71 201 239 125 55 32 36 0 0
Totale 12.914