CINECA IRIS Institutional Research Information System

PACI, SANDRO
 Distribuzione geografica
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Continente #
NA - Nord America 22.592
AS - Asia 13.385
EU - Europa 10.336
SA - Sud America 2.547
Continente sconosciuto - Info sul continente non disponibili 924
AF - Africa 386
OC - Oceania 20
Totale 50.190
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Nazione #
US - Stati Uniti d'America 21.706
IT - Italia 4.235
SG - Singapore 3.987
CN - Cina 3.583
HK - Hong Kong 2.768
BR - Brasile 2.063
SE - Svezia 1.374
VN - Vietnam 1.300
BG - Bulgaria 1.056
DE - Germania 962
CA - Canada 651
FR - Francia 591
RU - Federazione Russa 443
FI - Finlandia 395
GB - Regno Unito 379
JP - Giappone 356
TR - Turchia 335
UA - Ucraina 259
KR - Corea 258
IN - India 196
AR - Argentina 184
BD - Bangladesh 130
CI - Costa d'Avorio 119
CH - Svizzera 91
MX - Messico 89
ES - Italia 88
AT - Austria 80
NL - Olanda 80
EC - Ecuador 72
ID - Indonesia 69
IQ - Iraq 69
ZA - Sudafrica 64
CO - Colombia 53
BE - Belgio 52
PK - Pakistan 51
VE - Venezuela 47
JM - Giamaica 39
NO - Norvegia 39
PL - Polonia 39
MA - Marocco 38
CZ - Repubblica Ceca 37
CL - Cile 31
EG - Egitto 31
SA - Arabia Saudita 31
UZ - Uzbekistan 30
PY - Paraguay 29
PE - Perù 28
TN - Tunisia 28
IR - Iran 27
NG - Nigeria 26
UY - Uruguay 25
KE - Kenya 23
CR - Costa Rica 22
GR - Grecia 21
AE - Emirati Arabi Uniti 20
LT - Lituania 20
MY - Malesia 20
RO - Romania 19
HN - Honduras 18
JO - Giordania 17
PH - Filippine 17
IL - Israele 14
AU - Australia 13
BO - Bolivia 13
NP - Nepal 13
TT - Trinidad e Tobago 13
AZ - Azerbaigian 12
HU - Ungheria 12
SI - Slovenia 12
ET - Etiopia 11
IE - Irlanda 11
NI - Nicaragua 10
DZ - Algeria 9
EU - Europa 9
KG - Kirghizistan 8
OM - Oman 8
SN - Senegal 8
AL - Albania 7
BH - Bahrain 7
BJ - Benin 7
GT - Guatemala 7
LB - Libano 7
TW - Taiwan 7
DO - Repubblica Dominicana 6
MO - Macao, regione amministrativa speciale della Cina 6
NZ - Nuova Zelanda 6
PT - Portogallo 6
TH - Thailandia 6
BB - Barbados 5
KZ - Kazakistan 5
PR - Porto Rico 5
SY - Repubblica araba siriana 5
GE - Georgia 4
PS - Palestinian Territory 4
AG - Antigua e Barbuda 3
BY - Bielorussia 3
DK - Danimarca 3
GH - Ghana 3
HR - Croazia 3
KW - Kuwait 3
Totale 49.204
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Città #
Hong Kong 2.726
Woodbridge 2.373
Ashburn 2.304
Singapore 2.077
Ann Arbor 1.507
Serra 1.506
San Jose 1.320
Houston 1.232
Santa Clara 1.022
Sofia 1.014
Chandler 1.010
Shanghai 1.008
Dallas 738
Milan 715
Beijing 705
New York 639
Fairfield 620
Council Bluffs 613
Ottawa 487
Seattle 469
Boardman 463
Princeton 381
Wilmington 362
Lawrence 358
Ho Chi Minh City 357
Lauterbourg 318
Los Angeles 311
Jacksonville 291
Tokyo 277
Hefei 262
Hanoi 254
Cambridge 226
Des Moines 226
Nanjing 191
Medford 184
Rome 181
Istanbul 180
São Paulo 173
Seoul 172
Buffalo 164
Helsinki 145
Dong Ket 144
Redondo Beach 142
Abidjan 119
Dearborn 117
Izmir 112
Frankfurt am Main 110
Pisa 99
Redwood City 91
Teramo 82
Columbus 80
Nanchang 78
Chicago 73
Boulder 71
Ogden 71
Orem 71
Bern 69
Changsha 64
Lucca 64
London 63
Guangzhou 62
Kunming 61
Munich 60
Phoenix 59
Rio de Janeiro 57
Shenyang 53
Nuremberg 51
Florence 50
Belo Horizonte 48
Vienna 48
Washington 48
Paris 47
Jüchen 44
Norwalk 44
Nürnberg 44
Hebei 41
Brussels 39
Oslo 39
Falkenstein 38
Madrid 38
Toronto 38
Montreal 37
San Vito Chietino 36
Basingstoke 35
Da Nang 35
Jiaxing 35
San Diego 35
Falls Church 34
Gif-sur-yvette 34
Haiphong 34
Mumbai 34
Brooklyn 33
Leopoldshafen 33
Atlanta 32
Dhaka 32
Brasília 30
Genoa 30
Campinas 29
Livorno 29
San Francisco 29
Totale 32.916
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Nome #
Final synthesis report on ASTEC 461
Appunti di Impianti Nucleari - Part III: Advanced Reactors 425
Validation of the ARIANNA-2 code on the basis of the HDR V44 and T31.5 Tests 419
Analysis of the External Radioactive Releases for An In-Vessel Break in a Fusion Plant using the ECART Code 359
Comparison report of the OECD/CSNI International Standard Problem 21 (PIPER-ONE experiment SB-7) 343
A knowledge-based approach for the structural assessment of cultural heritage, a case study: La Sapienza Palace in Pisa 325
Thermal-hydraulic Analysis of the LACE Experiments and its fall-out on the Safety Analysis of LWRs containment systems 270
First Outcomes from the PHEBUS FPT1 Uncertainty Application done in the EU-MUSA Project 269
SEAKNOT ‐ SEvere Accident KNOwledge Transfer to young generations 248
Analysis of an Ex-Vessel Break in the ITER Divertor Cooling Loop 237
Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP) 236
Sprays in Containment: Final results of the SARNET Spray Benchmark 233
Comparison and Analysis of the Condensation Benchmark Results 232
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 232
Thermal-hydraulic-iodine chemistry coupling: Insights gained from the SARNET benchmark on the THAI experiments Iod-11 and Iod-12 227
Lesson learned from the SARNET wall condensation benchmarks 225
Sprays in Containment: Final results of the SARNET Spray Benchmark 224
The MUSA Project: Management and Uncertainties of Severe Accidents 224
Validation of Severe Accident Codes Against PHEBUS FP Tests in the Framework of the PHEBEN-2 Project 223
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 222
Ex-Vessel Break in ITER Divertor Cooling Loop Analysis with the ECART Code 216
Validation of Severe Accident Codes Against Phebus FP for Plant Applications: Status of the PHEBEN2 Project 215
Spreading of Excellence in SARNET Network on Severe Accidents: the Education and Training Programme 214
Experimental and Numerical Analysis of the Air Inflow Technique for Dust Removal from the Vacuum Vessel of a Tokamak Machine 213
ASTEC code validation versus ICE P1-P8 experiments: comparison of two different experiences 212
Thermal hydraulic feasibility analysis of the IBED PHTS for ITER 209
Implementation and Validation of a Resuspension Model in MELCOR 1.8.6 for Fusion Applications 207
A model for simulating natural circulation phenomena in LWR containment system 204
ERMSAR-2015 conference of SARNET in the frame of the NUGENIA Technical Area 2 202
Dust mobilization experiments in the context of the fusion plants—STARDUST facility 199
Bases for dust mobilisation modelling in the light of STARDUST experiments 199
SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour 198
SARNET-2: Droplet Heat And Mass Transfer Elementary Benchmark - Comparison Report 197
Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes - The FPT-0 Test 196
Improvement of RELAP5/MOD1 and Application of the New Code Version to ISP 15 Post-Test Analysis 195
Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB 195
Validation of the ECART code for the safety analysis of fusion reactors 194
The Severe Accident Phenomenology Short Course (SAP): 12 years of excellence for dissemination of Severe Accident knowledge at international level 192
Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA 192
Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor 189
Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803 187
Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding 184
Realistic simulation of Thermalhydraulic transients in full pressure containment system during severe accidents 183
Generic Containment: Detailed comparison of containment simulations performed on plant scale 183
Stand-alone Containment Analysis of the Phébus FPT-1 test with the ASTEC and the MELCOR codes 181
Analysis of the influence of the heat transfer phenomena on the late phase of the ThAI Iod-11 and Iod-12 tests 180
OECD NEA Sample Problem Analysis with RELAP5/MOD1-019 Computer Code 177
Effects Due to an Obstacle Presence in STARDUST Mobilization Experiments 176
Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations 174
Realistic Evaluation of the Safety Margins in Nuclear Containment Systems 173
Stand-alone containment analysis of the Phébus FPT-1 test with the ASTEC and the MELCOR codes 172
Comparison and Analysis of the Condensation Benchmark Results 171
Stand-alone Containment Analysis of four Phébus tests with the ASTEC and MELCOR codes 171
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 171
Challenges to Computing Buoyancy-Driven Flows in the Containment System of LWRs 167
Bases for Aerosol Resuspension Modelling in the Light of STORM Experiments 166
Il rinascimento nucleare sarà trainato dalla globalizzazione economica? 166
Code accuracy evaluation of ISP 35 calculations based on NUPEC M-7-1 test 166
The Safety Margins Evaluation in Next Generation of Nuclear Reactors 165
The European Research on Severe Accidents in Generation 2 and 3 Nuclear Power Plants 165
Status of the TA2/SARNET R&D activities 165
Validation of Severe Accident Codes Against Phebus FP for Plant Applications (PHEBEN2) 164
Thermal Hydraulics Analysis of Integrated Blanket ELMS and Divertor Primary Heat Transfer System of ITER Fusion Reactor 164
A new integrated containment system for PWRs, able to mitigate severe accidents 164
Analysis of the OECD/CSNI ISP No. 46 on the PHEBUS FPT-1 Test Using the ECART 2k Code 164
Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5 163
In-Vessel Phase of the Benchmark Exercise on an Alternative TMI-2 Accident Scenario 163
Stand-alone containment analysis of the Phébus FPT-3 test with the ASTEC and the MELCOR codes 163
Vapour Condensation in Presence of Air in the TOSQAN Facility: A Computational Analysis 160
The 10th European Review Meeting on Severe Accident Research ERMSAR 2022: Severe Accident Research Eleven Years after the Fukushima Accident 160
Evaluation of Containment Heat and Mass Transfer Models with Consideration on the PHEBUS-FP Containment Vessel 159
ERMSAR-2017 conference of NUGENIA/SARNET on research on severe accidents in nuclear power plants 159
Stand-alone containment analysis of the Phébus FPT tests with the ASTEC and the MELCOR codes: the FPT-2 test 158
MELCOR 2.2 Modelling for Fusion Reactor Analysis 158
Heat and Mass Transfer Models in LWRs Containment Systems 157
Experimental and Computational Analysis of Steam Condensation in the Presence of Air and Helium 156
Bases for Dust Mobilisation Modelling in the Light of STARDUST Experiments 155
The Coupled Phenomenology of Accident Evolution for Primary System and Containment in Innovative LWRs 153
Effects of Spray/Walls Interactions in TOSQAN Tests 151
Modelling Requirements for Source Term Evaluation in Simplified LWRs 151
An Integrated Approach to the Hydrogen Challenge in the Containment System of Advanced LWRs 151
OECD-CSNI Containment Standard Problem N. 3: Calculation Results Using ARIANNA Computer Code 151
Environmental Source terms during a few Reference Accident Sequences (RAS) of NET/ITER plant 149
Application of AFT Fathom code to steady-state thermal-hydraulics analysis of ITER Primary Heat Transfer Systems 149
Investigation on Gas Distribution Phenomena inside the Containment System of LWRs 148
Coupling between Primary and Secondary Systems in Water Reactors with Passive Safety Features 148
Towards a decarbonised world 148
Ex Vessel LOCA Detection for a Primary Heat Transfer System of Fusion Plants 147
NBI Design Change Requests: Accident Analyses and ORE Assessment in the New Configuration 147
The Problem of the Thermal-hydraulic Transient Inside Full Pressure Containment System Following a LOCA 146
Evaluation of Heat and Mass Transfer Models in LWRs Containment Systems 145
DCMN Calculations for the ISP-40 on STORM Test SR-11 Using the ECART Computer Code 145
Uncertainties of Source Term Assessments (USTA): An Indispensable Project 145
Methodologies for the safety analysis of innovative nuclear systems 144
Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA 144
Bases for Dust Mobilisation Modelling in the Light of Stardust Experiments 143
Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA 142
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project 142
SARNET2 Short Course on Severe Accident Phenomenology 141
Analisi dello stato dell'arte sul coefficiente di scambio termico con vapore in condensazione nei sistemi di contenimento dei reattori nucleari 141
Totale 19.253
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Categoria #
all - tutte 135.103
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 135.103
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20223.283 0 0 111 207 745 534 117 182 151 137 218 881
2022/20233.284 560 362 288 305 309 434 72 231 533 20 124 46
2023/20243.354 311 302 358 232 479 613 423 78 86 35 80 357
2024/202510.465 53 504 221 472 775 774 1.128 740 1.332 1.556 1.100 1.810
2025/202611.905 349 1.580 1.434 1.698 1.110 1.178 1.579 496 652 939 510 380
2026/20273.466 399 1.140 1.927 0 0 0 0 0 0 0 0 0
Totale 50.190