CINECA IRIS Institutional Research Information System

FORASASSI, GIUSEPPE
 Distribuzione geografica
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Continente #
NA - Nord America 10.810
EU - Europa 5.961
AS - Asia 4.765
SA - Sud America 538
AF - Africa 83
OC - Oceania 5
Continente sconosciuto - Info sul continente non disponibili 4
Totale 22.166
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Nazione #
US - Stati Uniti d'America 10.488
PL - Polonia 2.614
SG - Singapore 1.546
CN - Cina 1.435
IT - Italia 1.151
HK - Hong Kong 716
BR - Brasile 464
VN - Vietnam 414
SE - Svezia 391
BG - Bulgaria 384
CA - Canada 284
UA - Ucraina 252
DE - Germania 249
FI - Finlandia 211
TR - Turchia 201
FR - Francia 171
RU - Federazione Russa 159
KR - Corea 156
CH - Svizzera 144
GB - Regno Unito 104
JP - Giappone 99
IN - India 59
AT - Austria 58
BD - Bangladesh 28
AR - Argentina 26
BJ - Benin 24
IQ - Iraq 20
SA - Arabia Saudita 20
ZA - Sudafrica 20
MX - Messico 17
CO - Colombia 14
ES - Italia 14
BE - Belgio 13
ID - Indonesia 11
IE - Irlanda 11
EC - Ecuador 10
NL - Olanda 10
PK - Pakistan 10
CI - Costa d'Avorio 9
PH - Filippine 8
VE - Venezuela 8
ET - Etiopia 6
AZ - Azerbaigian 5
CL - Cile 5
TN - Tunisia 5
UY - Uruguay 5
UZ - Uzbekistan 5
CR - Costa Rica 4
JM - Giamaica 4
KE - Kenya 4
MY - Malesia 4
RO - Romania 4
SY - Repubblica araba siriana 4
AU - Australia 3
CZ - Repubblica Ceca 3
DZ - Algeria 3
EU - Europa 3
IL - Israele 3
MA - Marocco 3
PE - Perù 3
TT - Trinidad e Tobago 3
AE - Emirati Arabi Uniti 2
AL - Albania 2
BB - Barbados 2
EE - Estonia 2
GE - Georgia 2
GR - Grecia 2
HU - Ungheria 2
KH - Cambogia 2
KZ - Kazakistan 2
LK - Sri Lanka 2
OM - Oman 2
PA - Panama 2
PY - Paraguay 2
RS - Serbia 2
SK - Slovacchia (Repubblica Slovacca) 2
SV - El Salvador 2
TH - Thailandia 2
AM - Armenia 1
AO - Angola 1
BM - Bermuda 1
BO - Bolivia 1
BW - Botswana 1
BY - Bielorussia 1
CG - Congo 1
DO - Repubblica Dominicana 1
EG - Egitto 1
GA - Gabon 1
HN - Honduras 1
HR - Croazia 1
IR - Iran 1
JO - Giordania 1
KG - Kirghizistan 1
LT - Lituania 1
LU - Lussemburgo 1
LY - Libia 1
MD - Moldavia 1
MP - Marianne Settentrionali, isole 1
NG - Nigeria 1
NI - Nicaragua 1
Totale 22.158
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Città #
Woodbridge 1.514
Ann Arbor 1.226
Ashburn 874
Houston 854
Singapore 828
Hong Kong 708
Chandler 647
Milan 579
Fairfield 561
Santa Clara 554
San Jose 470
Jacksonville 383
Sofia 383
Dallas 321
Beijing 299
Shanghai 295
Seattle 267
Ottawa 261
Wilmington 224
New York 220
Hefei 173
Cambridge 170
Boardman 165
Nanjing 155
Lawrence 151
Princeton 151
Seoul 147
Izmir 138
Bern 132
Lauterbourg 128
Des Moines 116
Los Angeles 104
Dong Ket 102
Medford 98
Tokyo 97
Ho Chi Minh City 75
Council Bluffs 68
Serra 68
Hanoi 67
Jüchen 60
Buffalo 59
Nanchang 57
Vienna 56
Helsinki 54
Dearborn 47
Rome 46
Boulder 45
Istanbul 41
Redondo Beach 36
Kunming 33
Frankfurt am Main 31
São Paulo 29
Ogden 27
Norwalk 25
Cotonou 24
Hebei 24
Florence 23
Shenyang 23
Jiaxing 22
Redwood City 22
Changsha 20
Columbus 19
San Diego 19
Tianjin 18
The Dalles 17
Orem 16
Rio de Janeiro 16
Chicago 15
Manchester 14
Guangzhou 13
Brussels 12
Chennai 12
Da Nang 12
Kocaeli 12
Belo Horizonte 11
Curitiba 11
Falls Church 11
Orange 11
Tezze Sul Brenta 11
Brooklyn 10
Dublin 10
Jinan 10
Phoenix 10
Riyadh 10
Zhengzhou 10
Dhaka 9
Salvador 9
Abidjan 8
Düsseldorf 8
Hangzhou 8
Jeddah 8
Lanzhou 8
Quanzhou 8
San Francisco 8
Tortona 8
Washington 8
Amsterdam 7
Auburn Hills 7
Boston 7
Haiphong 7
Totale 15.005
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Nome #
Buckling of thin cylindrical shell subject to uniform external pressure 1.643
Seismic response of reactor vessel internals in the IRIS reactor 1.240
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
PRELIMINARY EVALUATION OF CORE COMPACTION PHENOMENON: METHODOLOGICAL APPROACH 193
Preliminary evaluation of the seismic response of the ELSY LFR 190
Seismic response of reactor vessel internals in the IRIS reactor 185
" Siar: Valutazione del Rischio nel Trasporto di Materiali Pericolosi" 180
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 180
Wastes Management Through Transmutation in an ADS Reactor 175
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 175
Preliminary Set Up of the Methodology to Analyze Nuclear Fuel Cycle Scenarios 174
Spent Nuclear Fuel Radiotoxicity Evaluation in the context of Minor Actinides Management with ADS Systems 169
Thermal analysis of a spent fuel cask in different transport conditions 169
Preliminary evaluation of the seismic response of the ELSY LFR 169
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 169
THE CAPABILITIES OF HTRS TO BURN ACTINIDES AND TO OPTIMIZE PLUTONIUM EXPLOITATION 167
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 167
Evaluation of safety performances of a superficial disposal facility subject to an aircraft impact and fuel burning 166
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 165
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 164
DYNAMIC RESPONSE OF A NUCLEAR POWER PLANT SUBJECTED TO EXTERNAL ACCIDENT EVENT 164
Simulation of a crash-box for racing car based on sandwich material, 162
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 162
Preliminary evaluation of aircraft impact on a near term nuclear power plant 162
Buckling of thin cylindrical shell subject to uniform external pressure 161
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 161
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 161
Influence of the curved geometrical shape on the thin shell buckling phenomenon behaviour 159
"ATHERMIP Project and Airlock Structural and Capability Analysis in Accident Conditions" 158
Buckling of imperfect cylindrical shell under lateral pressure 158
Preliminary evaluation of the safety margin of a Gen II reactor subjected to an aircraft impact 158
Spent fuel transport cask thermal evaluation under normal and accident conditions 156
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 156
Earthquake response analysis of reactor vessel internals for next generation reactors 155
Preliminary evaluation of structural response of ELSY reactor in the after shutdown condition 155
Honeycomb sandwich material modelling for dynamic simulations of a crash-box for racing car 154
Impact analysis of a crash-box for racing car in sandwich material, 153
Experimental study on combined natural and gas-injection enhanced circulation 153
Evaluation of damaging effects on a NPP integrity subjected to beyond design earthquake 153
Horizontal drop test evaluation of a packaging system 153
Crushing behaviour of honeycomb structures –numerical simulation and experiment, 152
Seismic analysis approach applied to a small size next generation nuclear reactor 152
Preliminary seismic analysis of a next generation NPP 151
Numerical evaluation of sloshing effects in ELSY innovative nuclear reactor pressure vessels seismic response 151
Thermal analysis of a spent fuel cask in different transport conditions 150
SEISMIC SAFETY MARGIN OF AN ISOLATED SMR REACTOR UNDER SEVERE EARTHQUAKE 150
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization, 149
Conceptual evaluation of fluid-structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor 148
A Type b(u) package to store and transport medical sources 145
Influence of aircraft impact on seismic isolated SMR reactor 145
"Benchmark on Containment Penetration Sealing Areas Behaviour (ATHERMIP)" 144
Experimental study on combined natural and gas-injection enhanced circulation 144
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 144
GLOBAL STRUCTURAL RESPONSE OF AN SMR REACTOR SUBJECTED TO AN AIRCRAFT IMPACT 144
Ultimate Resistance of a Reinforced Concrete Foundation Under Impulsive Loading, Structural Mechanical in Reactor Technology, vol. H, pp. 534-542, Prague 2003 142
Curved shape influence on buckling thin shell behaviour 142
Numerical and experimental evaluations of the effects of a packaging system free drop 141
Experimental Study on Combined Natural and enhanced Circulation, 139
Curved thin shell buckling behaviour 139
Seismic response of reactor vessel internals in the IRIS reactor 139
Preliminary evaluation of the flooding effects on an existing PWR 139
Preliminary Evaluation of Aircraft Impact on a Near Term Nuclear Power Plant 138
Natural and Gas Injection Enhanced Circulation in a Loop with Variable Friction, GENES4/ANP Int. Conf., Kyoto (Japan) Sept. 15-19, 2003 137
Instabilities influence on thin shell buckling behaviour 137
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
"Comparison of some Passive Safety Concept in Nuclear and Process Industry System" 136
Preliminary analysis of the structural effects due to dynamic loads of the isolated next generation lead cooled reactor 136
Available computational tools and models for structural and thermal fluid dynamic analyses of the core catcher 136
Dynamic behaviour of a crash-box in sandwich material, 135
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 135
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 134
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization, 133
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 133
Buckling of imperfect cylindrical shell under lateral pressure 133
Seismic analysis approach applied to a small size next generation nuclear reactor 133
Ultimate Seismic Analyssis of Shear Walls by a FEM Code 131
Fluid-Dynamic Characterization of ADS-DF Nuclear Reactor Fuel Element 130
Experimental Investigation on Natural and Gas Enhanced Circulation, 130
EVALUATION OF THE ISOLATION SYSTEM INFLUENCE IN THE SEISMIC LOADING ANALISYS APPLIED TO A NEAR TERM DEPLOYMENT REACTOR 130
Experimental Investigation on Natural and Gas-injection Enhanced Circulation 130
Numerical and experimental analysis of the impact of a nuclear spent fuel cask 129
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 128
Earthquake response analysis of reactor vessel internals for next generation reactors 128
Implementation and Preliminary Verification of the RLAP/PARKS Code for Pb-Bi Cooled Subcritical Systems, 126
Contribution to Long Term Minor Actinides Management through Transmutation in Accelerator Driven Systems (ADS) 126
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 126
The Capability of HTRs to Burn Actinides and to Optimize Plutonium Exploitation, Int Conf. ICONE 12, Arlington (USA) April, 2004 124
Preliminary evaluation of a severe flooding effects on an innovative SMR 124
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 124
Cytodiagnosis of pleural effusions. II. Non-neoplastic effusions and their cytomorphological characterization 121
Evaluation Of Instability Of Laminated Rubber Bearings Under Dynamic Loading 121
Preliminary safety evaluation of an aircraft impact on a near-surface RWs repository 121
Inclined DROP test of A CC-440 packaging system 121
IN-VESSEL CORE RETENTION STRATEGY (IVCRS) 120
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 119
Dynamic buckling in a next generation metal coolant nuclear reactor 118
Totale 17.543
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Categoria #
all - tutte 53.897
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 53.897
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20221.247 3 143 31 68 258 187 21 61 53 14 60 348
2022/20231.546 192 101 69 173 228 289 4 122 255 15 82 16
2023/20244.365 318 255 308 141 260 222 34 34 21 2.626 27 119
2024/20253.714 33 189 43 155 382 347 313 177 386 551 383 755
2025/20263.473 157 526 359 175 335 452 611 139 168 331 174 46
2026/202734 34 0 0 0 0 0 0 0 0 0 0 0
Totale 22.252