CINECA IRIS Institutional Research Information System

LO FRANO, ROSA
 Distribuzione geografica
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Continente #
NA - Nord America 12.360
AS - Asia 6.404
EU - Europa 4.525
SA - Sud America 828
AF - Africa 193
OC - Oceania 15
Continente sconosciuto - Info sul continente non disponibili 9
AN - Antartide 1
Totale 24.335
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Nazione #
US - Stati Uniti d'America 12.094
SG - Singapore 2.159
IT - Italia 1.966
CN - Cina 1.720
HK - Hong Kong 1.007
BR - Brasile 687
VN - Vietnam 670
SE - Svezia 444
DE - Germania 401
FR - Francia 350
BG - Bulgaria 346
FI - Finlandia 222
CA - Canada 199
RU - Federazione Russa 190
GB - Regno Unito 178
JP - Giappone 159
KR - Corea 140
IN - India 117
TR - Turchia 86
UA - Ucraina 83
BD - Bangladesh 74
CH - Svizzera 60
MA - Marocco 58
AR - Argentina 53
AT - Austria 49
NL - Olanda 44
ID - Indonesia 40
IQ - Iraq 40
MX - Messico 40
SA - Arabia Saudita 36
BE - Belgio 34
ES - Italia 34
ZA - Sudafrica 33
PL - Polonia 32
IE - Irlanda 28
BJ - Benin 23
EC - Ecuador 20
PK - Pakistan 19
CI - Costa d'Avorio 18
UZ - Uzbekistan 16
UY - Uruguay 15
VE - Venezuela 15
CO - Colombia 14
MY - Malesia 13
AU - Australia 11
PH - Filippine 11
RO - Romania 11
TN - Tunisia 11
IR - Iran 10
KE - Kenya 9
NG - Nigeria 9
TW - Taiwan 9
CL - Cile 8
EG - Egitto 8
KZ - Kazakistan 8
AZ - Azerbaigian 7
CZ - Repubblica Ceca 7
IL - Israele 7
PE - Perù 7
AE - Emirati Arabi Uniti 6
EU - Europa 6
RS - Serbia 6
BY - Bielorussia 5
EE - Estonia 5
ET - Etiopia 5
GE - Georgia 5
JM - Giamaica 5
LT - Lituania 5
NP - Nepal 5
PY - Paraguay 5
SN - Senegal 5
AM - Armenia 4
CR - Costa Rica 4
HU - Ungheria 4
JO - Giordania 4
KG - Kirghizistan 4
OM - Oman 4
PT - Portogallo 4
TH - Thailandia 4
TT - Trinidad e Tobago 4
AL - Albania 3
GR - Grecia 3
LB - Libano 3
LK - Sri Lanka 3
SY - Repubblica araba siriana 3
BB - Barbados 2
BN - Brunei Darussalam 2
BO - Bolivia 2
BS - Bahamas 2
CG - Congo 2
DK - Danimarca 2
DO - Repubblica Dominicana 2
DZ - Algeria 2
HN - Honduras 2
KW - Kuwait 2
LA - Repubblica Popolare Democratica del Laos 2
NZ - Nuova Zelanda 2
PA - Panama 2
PS - Palestinian Territory 2
UG - Uganda 2
Totale 24.303
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Città #
Woodbridge 1.248
Singapore 1.217
Ashburn 1.071
Ann Arbor 1.043
Hong Kong 978
Houston 938
Fairfield 813
San Jose 789
Santa Clara 746
Dallas 620
Chandler 541
Serra 408
Shanghai 371
Seattle 370
Sofia 346
Beijing 345
Wilmington 293
Cambridge 286
New York 273
Milan 230
Boardman 208
Ho Chi Minh City 168
Hefei 163
Los Angeles 162
Princeton 160
Ottawa 151
Lawrence 149
Des Moines 145
Lauterbourg 135
Tokyo 132
Hanoi 131
Medford 118
Dong Ket 103
Seoul 101
Florence 96
Nanjing 88
Frankfurt am Main 87
Pisa 85
Helsinki 79
Jacksonville 78
Munich 78
Buffalo 70
Lucca 68
Rome 61
Redondo Beach 60
Council Bluffs 53
Dearborn 51
São Paulo 51
Columbus 45
Marseille 43
Casablanca 42
Vienna 40
Boulder 36
San Diego 35
Ogden 33
Redwood City 33
Bern 32
Turku 32
Kunming 30
Orem 29
London 28
San Vito Chietino 28
Dhaka 27
Istanbul 27
The Dalles 27
Dublin 26
Nanchang 26
Rio de Janeiro 25
Chennai 24
Belo Horizonte 23
Brussels 23
Chicago 23
Cotonou 23
Falkenstein 23
Guangzhou 23
Haiphong 23
Izmir 23
Châteauneuf-le-rouge 22
Da Nang 22
Falls Church 22
Fuzhou 22
Nuremberg 22
Atlanta 21
Riyadh 21
Shenyang 21
San Francisco 20
Baghdad 19
Abidjan 18
Livorno 18
Tezze Sul Brenta 18
Salvador 17
Turin 17
Düsseldorf 16
Hebei 16
Johannesburg 16
Mexico City 16
Montreal 16
Norwalk 16
Quanzhou 16
Volterra 16
Totale 17.237
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Nome #
LFR safety approach and main ELFR safety analysis results 313
METHODOLOGY TO INVESTIGATE VIBRATION PHENOMENA CAUSED BY THE STEAM CONDENSATION AT SUB-ATMOSPHERIC CONDITION 275
Thermal Tests Of A CP5.2 Packaging System: Post Experimental Test Description 270
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 235
PRELIMINARY ASSESSMENT OF THE FLUID-STRUCTURE INTERACTION EFFECTS IN A GEN IV LMR 233
ANALYSIS OF SEISMIC ISOLATION PROBLEMS OF NPP BUILDINGS 228
PRELIMINARY EVALUATION OF THE RELIABILITY OF GEN II OR III REACTORS IN BDBE CONDITIONS 225
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 216
Mitigation of a Loss of Coolant Accident in ITER Vacuum Vessel by Means of Steam Pressure Suppression 213
Aircraft Impact onto an existing nuclear plant 206
Manufacturing challenges and required R&D on fusion pebbles bed material 202
Application of PHADEC method for the decontamination of radioactive steam piping components 199
Three-dimensional condensation regime diagram for direct contact condensation of steam injected into water at subatmospheric conditions 198
Feasibility study of desalination plant powered by SMR 195
PRELIMINARY EVALUATION OF CORE COMPACTION PHENOMENON: METHODOLOGICAL APPROACH 193
THERMAL TESTS OF A CP5.2 PACKAGING SYSTEM: PROTOTYPE AND EXPERIMENTAL TEST DESCRIPTION 192
Thermo-mechanical test rig for experimental evaluation of thermal conductivity of ceramic pebble beds 191
Analysis of vibrations due to the steam condensation at sub-atmospheric condition 189
Analysis of the effects caused by the core compaction into LFR reactor 186
Experimental analysis of steam condensation patterns within a pressure suppression system operating at sub-atmospheric pressure conditions 185
Experimental investigation of functional performance of a vacuum vessel pressure suppression system of ITER 180
Application of PHADEC method for the decontamination of radioactive steam piping components of Caorso plant 178
Experimental investigation of steam condensation in water tank at sub-atmospheric pressure 178
Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor 177
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 175
Lithium orthosilicate as nuclear fusion breeder material: Optimization of the drip casting production technology 175
CHARACTERIZATION OF FUTURIX-FTA IRRADIATED NUCLEAR FUEL SAMPLES 173
Investigation of liquid metal embrittlement of AISI 316L steels 173
Design methodology of multi-hole spargers to prevent steam coalescence at sub-atmospheric pressure 171
Analysis of hydrogen deflagration/detonation effects in vacuum pressure suppression tank 171
Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket 168
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 167
Evaluation of safety performances of a superficial disposal facility subject to an aircraft impact and fuel burning 166
Demonstration of structural performance of IP-2 package by simulation and full-scale horizontal free drop test 166
Thermal tests of a CP5.2 packaging system: Prototype and experimental test description 166
Preliminary evaluation of the seismic response of the ELSY LFR 165
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 164
Investigation of vibrations caused by the steam condensation at sub-atmospheric condition in VVPSS 164
Integrity of pressure vessel lower head in case of corium relocation: identification of loads and failure modes 164
Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials 163
Preliminary Analysis of Creep and Ageing Influence During SBO 163
Preliminary evaluation of aircraft impact on a near term nuclear power plant 162
Numerical-experimental analyses by Hot-Wire method of an alumina cylinder for future studies on thermal conductivity of the fusion breeder materials 162
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 161
CFD thermal analysis of ITER pressure suppression tanks 161
Buckling of thin cylindrical shell subject to uniform external pressure 160
Dismantling of the graphite pile of Latina NPP: Characterization and handling/removal equipment for single brick or multi-bricks 159
Handling and conditioning techniques of activated chips for the decommissioning of the E. Fermi nuclear power plant 158
Preliminary evaluation of the safety margin of a Gen II reactor subjected to an aircraft impact 157
Manufacturing Technology And Properties Of Ceramic Pebbles For Breeding Blanket 157
Manufacturing technology of ceramic pebbles for breeding blanket 157
Feasibility study of a new fabrication method for the Li4Sio4 pebbles 157
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 156
Conceptual evaluation of fluid-structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor 155
Influence of the curved geometrical shape on the thin shell buckling phenomenon behaviour 155
Analysis Of The Core Compaction Phenomenon 155
Thermal tests of a scaled down mock-up of CP5.2 packaging system: Post-test analysis 155
Preliminary evaluation of structural response of ELSY reactor in the after shutdown condition 154
Evaluation of damaging effects on a NPP integrity subjected to beyond design earthquake 152
Horizontal drop test evaluation of a packaging system 152
Thermodynamics of the Lithium Loop in a Liquid Metal Divertor for Future Fusion Reactors 152
Experimental thermal characterization of concrete to be used in CP5.2 packaging system 152
Direct condensation of steam in a water tank at subatmospheric Pressures’ 152
Rigorous Dynamic Simulation of Cryogenic Distillation of Hydrogen Isotopologues in the Fuel Cycle of a Thermonuclear Reactor Based on UV Flash 152
Seismic analysis approach applied to a small size next generation nuclear reactor 151
Enhanced radioactive waste drum monitoring: A sensorized LoRa-based network for identification and integrity assessment 150
An improved substructuring approach for dynamic modelling – The example of the ITER vacuum vessel 150
Thermal analysis of a spent fuel cask in different transport conditions 148
SEISMIC SAFETY MARGIN OF AN ISOLATED SMR REACTOR UNDER SEVERE EARTHQUAKE 148
ORIGINAL CORE CATCHER DESIGN IN ORDER TO MANAGE THE CORE MELTDOWN SEVERE ACCIDENT WITH THE IN-VESSEL RETENTION STRATEGY 148
Thermo-mechanical characterization of ceramic pebbles for breeding blanket 146
GLOBAL STRUCTURAL RESPONSE OF AN SMR REACTOR SUBJECTED TO AN AIRCRAFT IMPACT 144
Influence of aircraft impact on seismic isolated SMR reactor 144
null 143
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 143
Investigation on thermal treatments of high-resistance austenitic stainless steels employed as structural materials in generation IV reactors 143
Experimental thermal characterization of concrete to be used in CP5.2 packaging system 142
Performances of the ITER Pressure Suppression System during unstable steam condensation regimes 140
Numerical and experimental evaluations of the effects of a packaging system free drop 140
Post-test of the sgtr experimental tests carried out in the LIFUS facility 139
Preliminary Evaluation of Aircraft Impact on a Near Term Nuclear Power Plant 138
Preliminary evaluation of the flooding effects on an existing PWR 138
null 138
Isolation systems influence in the seismic loading propagation analysis applied to an innovative near term reactor 137
Safety performance of a near surface repository subject to a fuel burning 137
Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance 136
Seismic response of reactor vessel internals in the IRIS reactor 136
External Event Risk Assessment: Methodology and Application 134
EM zooming procedure in ANSYS Maxwell 3D 134
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 133
Buckling of imperfect cylindrical shell under lateral pressure 133
Structural performance of an IP2 package in free drop test conditions: numerical and experimental evaluations 132
Simplified Models of the ITER Vacuum Vessel for Global Seismic Analyses 132
Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant 132
Computational fluid dynamics thermal analysis of ITER pressure suppression tanks 132
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 131
Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles 131
EVALUATION OF THE ISOLATION SYSTEM INFLUENCE IN THE SEISMIC LOADING ANALISYS APPLIED TO A NEAR TERM DEPLOYMENT REACTOR 129
Earthquake response analysis of reactor vessel internals for next generation reactors 128
ITER cryostat accidental scenario: fluid dynamics analysis of Ingress of Coolant Event Accident 128
Totale 16.492
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Categoria #
all - tutte 73.869
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 73.869
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021297 0 0 0 0 0 0 0 0 0 0 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
2025/20266.240 308 761 736 526 660 571 1.178 329 369 615 187 0
Totale 24.693