CINECA IRIS Institutional Research Information System

FORASASSI, GIUSEPPE
 Distribuzione geografica
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Continente #
NA - Nord America 11.846
EU - Europa 5.986
AS - Asia 4.780
SA - Sud America 562
Continente sconosciuto - Info sul continente non disponibili 90
AF - Africa 87
OC - Oceania 5
Totale 23.356
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Nazione #
US - Stati Uniti d'America 11.469
PL - Polonia 2.615
SG - Singapore 1.550
CN - Cina 1.436
IT - Italia 1.168
HK - Hong Kong 717
BR - Brasile 486
VN - Vietnam 415
SE - Svezia 391
BG - Bulgaria 384
CA - Canada 312
UA - Ucraina 252
DE - Germania 250
FI - Finlandia 211
TR - Turchia 202
FR - Francia 171
RU - Federazione Russa 159
KR - Corea 157
CH - Svizzera 144
GB - Regno Unito 105
JP - Giappone 99
IN - India 59
AT - Austria 58
BD - Bangladesh 30
AR - Argentina 27
BJ - Benin 24
IQ - Iraq 20
SA - Arabia Saudita 20
ZA - Sudafrica 20
MX - Messico 17
ES - Italia 15
CO - Colombia 14
JM - Giamaica 14
BE - Belgio 13
ID - Indonesia 12
IE - Irlanda 12
CR - Costa Rica 10
EC - Ecuador 10
NL - Olanda 10
PK - Pakistan 10
CI - Costa d'Avorio 9
PH - Filippine 9
VE - Venezuela 8
CL - Cile 6
ET - Etiopia 6
AZ - Azerbaigian 5
NI - Nicaragua 5
TN - Tunisia 5
UY - Uruguay 5
UZ - Uzbekistan 5
KE - Kenya 4
MA - Marocco 4
MY - Malesia 4
RO - Romania 4
SV - El Salvador 4
SY - Repubblica araba siriana 4
TT - Trinidad e Tobago 4
AU - Australia 3
CZ - Repubblica Ceca 3
DZ - Algeria 3
EU - Europa 3
GT - Guatemala 3
IL - Israele 3
KZ - Kazakistan 3
PE - Perù 3
TH - Thailandia 3
AE - Emirati Arabi Uniti 2
AL - Albania 2
BB - Barbados 2
CG - Congo 2
EE - Estonia 2
EG - Egitto 2
GE - Georgia 2
GR - Grecia 2
HN - Honduras 2
HR - Croazia 2
HU - Ungheria 2
KH - Cambogia 2
LK - Sri Lanka 2
LT - Lituania 2
MD - Moldavia 2
OM - Oman 2
PA - Panama 2
PY - Paraguay 2
RS - Serbia 2
SK - Slovacchia (Repubblica Slovacca) 2
AM - Armenia 1
AO - Angola 1
BM - Bermuda 1
BO - Bolivia 1
BW - Botswana 1
BY - Bielorussia 1
DO - Repubblica Dominicana 1
GA - Gabon 1
GH - Ghana 1
IR - Iran 1
JO - Giordania 1
KG - Kirghizistan 1
LU - Lussemburgo 1
LY - Libia 1
Totale 23.260
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Città #
Woodbridge 1.515
Ann Arbor 1.226
Ashburn 984
Houston 856
Singapore 829
Hong Kong 709
Chandler 647
Milan 583
Santa Clara 564
Fairfield 562
San Jose 550
Jacksonville 383
Sofia 383
Dallas 335
Beijing 300
Shanghai 295
Seattle 269
Council Bluffs 261
Ottawa 261
New York 231
Wilmington 224
Hefei 173
Cambridge 170
Boardman 165
Nanjing 155
Lawrence 151
Princeton 151
Seoul 148
Izmir 138
Bern 132
Lauterbourg 128
Los Angeles 124
Des Moines 116
Dong Ket 102
Medford 98
Tokyo 97
Ho Chi Minh City 75
Serra 68
Buffalo 67
Hanoi 67
Jüchen 60
Nanchang 57
Vienna 56
Helsinki 54
São Paulo 50
Dearborn 47
Rome 46
Boulder 45
Istanbul 42
Redondo Beach 36
Kunming 33
Frankfurt am Main 31
Ogden 27
Norwalk 25
Cotonou 24
Florence 24
Hebei 24
Shenyang 23
Jiaxing 22
Redwood City 22
Changsha 20
Chicago 20
Columbus 19
San Diego 19
Phoenix 18
Tianjin 18
The Dalles 17
Orem 16
Rio de Janeiro 16
Manchester 15
Brooklyn 13
Guangzhou 13
Toronto 13
Brussels 12
Chennai 12
Da Nang 12
Kocaeli 12
San Francisco 12
Belo Horizonte 11
Curitiba 11
Dublin 11
Falls Church 11
Orange 11
Tezze Sul Brenta 11
Dhaka 10
Jinan 10
Riyadh 10
Zhengzhou 10
Salvador 9
Abidjan 8
Boston 8
Düsseldorf 8
Hangzhou 8
Jeddah 8
Lanzhou 8
Miami 8
Montreal 8
Quanzhou 8
Tortona 8
Washington 8
Totale 15.520
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Nome #
Buckling of thin cylindrical shell subject to uniform external pressure 1.653
Seismic response of reactor vessel internals in the IRIS reactor 1.246
ANALYSIS OF SEISMIC ISOLATION PROBLEMS OF NPP BUILDINGS 240
PRELIMINARY ASSESSMENT OF THE FLUID-STRUCTURE INTERACTION EFFECTS IN A GEN IV LMR 238
PRELIMINARY EVALUATION OF THE RELIABILITY OF GEN II OR III REACTORS IN BDBE CONDITIONS 235
Analisi sperimentale della capacità di assorbimento di energia di superfici alettate in acciaio AISI 304 217
PRELIMINARY EVALUATION OF CORE COMPACTION PHENOMENON: METHODOLOGICAL APPROACH 201
Preliminary evaluation of the seismic response of the ELSY LFR 193
Seismic response of reactor vessel internals in the IRIS reactor 190
" Siar: Valutazione del Rischio nel Trasporto di Materiali Pericolosi" 189
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 188
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 188
Preliminary Set Up of the Methodology to Analyze Nuclear Fuel Cycle Scenarios 180
Wastes Management Through Transmutation in an ADS Reactor 179
Spent Nuclear Fuel Radiotoxicity Evaluation in the context of Minor Actinides Management with ADS Systems 174
Preliminary evaluation of the seismic response of the ELSY LFR 174
Evaluation of safety performances of a superficial disposal facility subject to an aircraft impact and fuel burning 174
A PRELIMINARY EVALUATION OF A GENERATION IV LIQUID METAL FAST REACTOR DUE TO SLOSHING AND THERMAL STRESS 174
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 173
Influence of non linear geometrical parameter on curved thin shell buckling behaviour 173
Thermal analysis of a spent fuel cask in different transport conditions 173
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 172
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 172
THE CAPABILITIES OF HTRS TO BURN ACTINIDES AND TO OPTIMIZE PLUTONIUM EXPLOITATION 171
Simulation of a crash-box for racing car based on sandwich material, 170
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 170
DYNAMIC RESPONSE OF A NUCLEAR POWER PLANT SUBJECTED TO EXTERNAL ACCIDENT EVENT 169
Preliminary evaluation of aircraft impact on a near term nuclear power plant 169
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 167
"ATHERMIP Project and Airlock Structural and Capability Analysis in Accident Conditions" 166
Preliminary evaluation of the safety margin of a Gen II reactor subjected to an aircraft impact 166
Influence of the curved geometrical shape on the thin shell buckling phenomenon behaviour 166
Buckling of imperfect cylindrical shell under lateral pressure 165
Buckling of thin cylindrical shell subject to uniform external pressure 164
Conceptual evaluation of fluid-structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor 164
Impact analysis of a crash-box for racing car in sandwich material, 163
Spent fuel transport cask thermal evaluation under normal and accident conditions 162
Earthquake response analysis of reactor vessel internals for next generation reactors 161
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 161
Evaluation of damaging effects on a NPP integrity subjected to beyond design earthquake 161
Preliminary evaluation of structural response of ELSY reactor in the after shutdown condition 161
Experimental study on combined natural and gas-injection enhanced circulation 160
Numerical evaluation of sloshing effects in ELSY innovative nuclear reactor pressure vessels seismic response 159
Honeycomb sandwich material modelling for dynamic simulations of a crash-box for racing car 159
SEISMIC SAFETY MARGIN OF AN ISOLATED SMR REACTOR UNDER SEVERE EARTHQUAKE 159
Crushing behaviour of honeycomb structures –numerical simulation and experiment, 157
Horizontal drop test evaluation of a packaging system 157
Seismic analysis approach applied to a small size next generation nuclear reactor 157
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization, 155
Preliminary seismic analysis of a next generation NPP 155
Thermal analysis of a spent fuel cask in different transport conditions 155
Influence of aircraft impact on seismic isolated SMR reactor 155
A Type b(u) package to store and transport medical sources 154
Conceptual evaluation of fluid-structure interaction effects coupled to a seismic event in an innovative liquid metal nuclear reactor 152
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 152
"Benchmark on Containment Penetration Sealing Areas Behaviour (ATHERMIP)" 151
Isolation systems influence in the seismic loading propagation analysis applied to an innovative near term reactor 150
GLOBAL STRUCTURAL RESPONSE OF AN SMR REACTOR SUBJECTED TO AN AIRCRAFT IMPACT 150
Numerical and experimental evaluations of the effects of a packaging system free drop 149
Curved shape influence on buckling thin shell behaviour 148
Experimental study on combined natural and gas-injection enhanced circulation 148
Preliminary Evaluation of Aircraft Impact on a Near Term Nuclear Power Plant 148
Ultimate Resistance of a Reinforced Concrete Foundation Under Impulsive Loading, Structural Mechanical in Reactor Technology, vol. H, pp. 534-542, Prague 2003 147
Preliminary evaluation of the flooding effects on an existing PWR 146
Curved thin shell buckling behaviour 145
Available computational tools and models for structural and thermal fluid dynamic analyses of the core catcher 145
Safety performance of a near surface repository subject to a fuel burning 145
Experimental Study on Combined Natural and enhanced Circulation, 144
Seismic response of reactor vessel internals in the IRIS reactor 144
Instabilities influence on thin shell buckling behaviour 143
Natural and Gas Injection Enhanced Circulation in a Loop with Variable Friction, GENES4/ANP Int. Conf., Kyoto (Japan) Sept. 15-19, 2003 142
Seismic analysis approach applied to a small size next generation nuclear reactor 142
"Comparison of some Passive Safety Concept in Nuclear and Process Industry System" 141
Preliminary analysis of the structural effects due to dynamic loads of the isolated next generation lead cooled reactor 141
Preliminary evaluation of seismic isolation effects in a Generation IV reactor 141
Buckling of imperfect cylindrical shell under lateral pressure 141
Dynamic behaviour of a crash-box in sandwich material, 140
SEISMIC ISOLATION OF THE IRIS NUCLEAR PLANT 140
Experimental Investigation on Natural and Gas Enhanced Circulation, 138
Preliminary seismic analysis of an innovative near term reactor: Methodology and application 138
Numerical and experimental analysis of the impact of a nuclear spent fuel cask 138
Ultimate Seismic Analyssis of Shear Walls by a FEM Code 137
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization, 137
Experimental Investigation on Natural and Gas-injection Enhanced Circulation 137
Fluid-Dynamic Characterization of ADS-DF Nuclear Reactor Fuel Element 136
Preliminary evaluation of steam generator tube rupture (SGTR) accident in lead cooled reactor 136
Contribution to Long Term Minor Actinides Management through Transmutation in Accelerator Driven Systems (ADS) 135
EVALUATION OF THE ISOLATION SYSTEM INFLUENCE IN THE SEISMIC LOADING ANALISYS APPLIED TO A NEAR TERM DEPLOYMENT REACTOR 134
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 133
Earthquake response analysis of reactor vessel internals for next generation reactors 133
Implementation and Preliminary Verification of the RLAP/PARKS Code for Pb-Bi Cooled Subcritical Systems, 132
The Capability of HTRs to Burn Actinides and to Optimize Plutonium Exploitation, Int Conf. ICONE 12, Arlington (USA) April, 2004 132
Preliminary evaluation of a severe flooding effects on an innovative SMR 131
Evaluation Of Instability Of Laminated Rubber Bearings Under Dynamic Loading 131
Influence of different foundation depths on the seismic response of a next generation nuclear reactor 130
Experimental evidence of imperfection influence on the buckling of thin cylindrical shell under uniform external pressure 127
IN-VESSEL CORE RETENTION STRATEGY (IVCRS) 126
Preliminary safety evaluation of an aircraft impact on a near-surface RWs repository 126
Cytodiagnosis of pleural effusions. II. Non-neoplastic effusions and their cytomorphological characterization 124
ANALYSIS OF SEISMIC ISOLATION PROBLEMS OF NPP BUILDINGS 124
Totale 18.304
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Categoria #
all - tutte 56.758
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 56.758
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20221.101 0 0 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
2026/20271.138 97 470 571 0 0 0 0 0 0 0 0 0
Totale 23.356