CINECA IRIS Institutional Research Information System

PACI, SANDRO
 Distribuzione geografica
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Continente #
NA - Nord America 19.626
AS - Asia 13.348
EU - Europa 10.237
SA - Sud America 2.518
AF - Africa 382
OC - Oceania 17
Continente sconosciuto - Info sul continente non disponibili 14
Totale 46.142
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Nazione #
US - Stati Uniti d'America 18.850
IT - Italia 4.157
SG - Singapore 3.983
CN - Cina 3.574
HK - Hong Kong 2.762
BR - Brasile 2.051
SE - Svezia 1.372
VN - Vietnam 1.299
BG - Bulgaria 1.056
DE - Germania 958
CA - Canada 607
FR - Francia 591
RU - Federazione Russa 443
FI - Finlandia 395
GB - Regno Unito 374
JP - Giappone 352
TR - Turchia 334
KR - Corea 258
UA - Ucraina 257
IN - India 194
AR - Argentina 181
BD - Bangladesh 127
CI - Costa d'Avorio 119
CH - Svizzera 90
ES - Italia 86
MX - Messico 86
AT - Austria 80
NL - Olanda 77
EC - Ecuador 70
ID - Indonesia 68
IQ - Iraq 68
ZA - Sudafrica 62
BE - Belgio 52
PK - Pakistan 51
CO - Colombia 46
VE - Venezuela 44
NO - Norvegia 39
PL - Polonia 39
MA - Marocco 38
CZ - Repubblica Ceca 37
SA - Arabia Saudita 31
EG - Egitto 30
UZ - Uzbekistan 30
CL - Cile 29
PY - Paraguay 29
PE - Perù 28
TN - Tunisia 28
IR - Iran 27
NG - Nigeria 26
UY - Uruguay 25
KE - Kenya 22
GR - Grecia 21
AE - Emirati Arabi Uniti 20
LT - Lituania 20
MY - Malesia 19
RO - Romania 19
JO - Giordania 17
JM - Giamaica 16
IL - Israele 14
PH - Filippine 14
BO - Bolivia 13
NP - Nepal 13
AZ - Azerbaigian 12
HN - Honduras 12
HU - Ungheria 12
ET - Etiopia 11
IE - Irlanda 11
AU - Australia 10
SI - Slovenia 10
TT - Trinidad e Tobago 10
DZ - Algeria 9
EU - Europa 9
CR - Costa Rica 8
OM - Oman 8
SN - Senegal 8
AL - Albania 7
BH - Bahrain 7
BJ - Benin 7
KG - Kirghizistan 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
NI - Nicaragua 5
SY - Repubblica araba siriana 5
GE - Georgia 4
GT - Guatemala 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
MN - Mongolia 3
Totale 46.073
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Città #
Hong Kong 2.721
Woodbridge 2.373
Singapore 2.076
Ashburn 1.833
Ann Arbor 1.507
Serra 1.506
Houston 1.224
San Jose 1.015
Sofia 1.014
Chandler 1.010
Shanghai 1.008
Santa Clara 1.001
Dallas 705
Beijing 702
Milan 697
Fairfield 620
New York 595
Ottawa 487
Seattle 464
Boardman 463
Princeton 381
Lawrence 358
Wilmington 358
Ho Chi Minh City 356
Lauterbourg 318
Jacksonville 289
Tokyo 275
Hefei 262
Hanoi 254
Los Angeles 247
Cambridge 226
Des Moines 226
Nanjing 191
Medford 184
Istanbul 180
Rome 175
Seoul 172
São Paulo 167
Helsinki 145
Dong Ket 144
Redondo Beach 142
Council Bluffs 141
Buffalo 135
Abidjan 119
Dearborn 117
Izmir 112
Frankfurt am Main 110
Pisa 97
Redwood City 91
Teramo 82
Nanchang 78
Columbus 76
Boulder 71
Ogden 71
Orem 71
Bern 69
Changsha 64
Lucca 64
Guangzhou 62
Kunming 61
London 61
Munich 60
Rio de Janeiro 57
Chicago 53
Shenyang 53
Nuremberg 51
Belo Horizonte 48
Vienna 48
Paris 47
Jüchen 44
Norwalk 44
Nürnberg 44
Florence 43
Hebei 41
Phoenix 40
Brussels 39
Oslo 39
Falkenstein 38
Madrid 38
San Vito Chietino 36
Basingstoke 35
Da Nang 35
Jiaxing 35
Falls Church 34
Gif-sur-yvette 34
Haiphong 34
San Diego 34
Leopoldshafen 33
Mumbai 33
Dhaka 32
Brasília 30
Campinas 29
Livorno 29
Tianjin 29
Washington 29
Amsterdam 28
Chennai 28
Genoa 28
Montreal 28
Turku 28
Totale 31.311
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Nome #
Final synthesis report on ASTEC 446
Appunti di Impianti Nucleari - Part III: Advanced Reactors 415
Validation of the ARIANNA-2 code on the basis of the HDR V44 and T31.5 Tests 413
Analysis of the External Radioactive Releases for An In-Vessel Break in a Fusion Plant using the ECART Code 353
A knowledge-based approach for the structural assessment of cultural heritage, a case study: La Sapienza Palace in Pisa 320
Thermal-hydraulic Analysis of the LACE Experiments and its fall-out on the Safety Analysis of LWRs containment systems 260
First Outcomes from the PHEBUS FPT1 Uncertainty Application done in the EU-MUSA Project 258
SEAKNOT ‐ SEvere Accident KNOwledge Transfer to young generations 236
Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP) 229
Analysis of an Ex-Vessel Break in the ITER Divertor Cooling Loop 228
Sprays in Containment: Final results of the SARNET Spray Benchmark 228
RELAP5/SIMMER-III code coupling development for PbLi-water interaction 222
Thermal-hydraulic-iodine chemistry coupling: Insights gained from the SARNET benchmark on the THAI experiments Iod-11 and Iod-12 219
Lesson learned from the SARNET wall condensation benchmarks 219
Comparison and Analysis of the Condensation Benchmark Results 218
ECART analysis of the STARDUST dust resuspension tests with an obstacle presence 217
The MUSA Project: Management and Uncertainties of Severe Accidents 217
Sprays in Containment: Final results of the SARNET Spray Benchmark 216
Validation of Severe Accident Codes Against Phebus FP for Plant Applications: Status of the PHEBEN2 Project 212
Ex-Vessel Break in ITER Divertor Cooling Loop Analysis with the ECART Code 211
Validation of Severe Accident Codes Against PHEBUS FP Tests in the Framework of the PHEBEN-2 Project 211
Experimental and Numerical Analysis of the Air Inflow Technique for Dust Removal from the Vacuum Vessel of a Tokamak Machine 208
Spreading of Excellence in SARNET Network on Severe Accidents: the Education and Training Programme 205
Implementation and Validation of a Resuspension Model in MELCOR 1.8.6 for Fusion Applications 203
Thermal hydraulic feasibility analysis of the IBED PHTS for ITER 200
A model for simulating natural circulation phenomena in LWR containment system 197
ERMSAR-2015 conference of SARNET in the frame of the NUGENIA Technical Area 2 197
ASTEC code validation versus ICE P1-P8 experiments: comparison of two different experiences 196
SARNET benchmark on Phébus FPT3 integral experiment on core degradation and fission product behaviour 194
Dust mobilization experiments in the context of the fusion plants—STARDUST facility 193
Bases for dust mobilisation modelling in the light of STARDUST experiments 191
Stand-Alone Containment Analysis of the Phébus FPT Tests with the ASTEC and the MELCOR Codes - The FPT-0 Test 191
Improvement of RELAP5/MOD1 and Application of the New Code Version to ISP 15 Post-Test Analysis 189
Validation of the ECART code for the safety analysis of fusion reactors 189
SARNET-2: Droplet Heat And Mass Transfer Elementary Benchmark - Comparison Report 189
Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA 188
Analysis of Test D1.1 of the LIFUS5/Mod3 facility for In-box LOCA in WCLL-BB 187
The Severe Accident Phenomenology Short Course (SAP): 12 years of excellence for dissemination of Severe Accident knowledge at international level 186
Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803 183
Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor 181
Generic Containment: Detailed comparison of containment simulations performed on plant scale 178
Realistic simulation of Thermalhydraulic transients in full pressure containment system during severe accidents 177
Analysis of the influence of the heat transfer phenomena on the late phase of the ThAI Iod-11 and Iod-12 tests 176
Stand-alone Containment Analysis of the Phébus FPT-1 test with the ASTEC and the MELCOR codes 173
OECD NEA Sample Problem Analysis with RELAP5/MOD1-019 Computer Code 172
Ability of Current Advanced Codes to Predict Core Degradation, Melt Progression and Reflooding 172
Realistic Evaluation of the Safety Margins in Nuclear Containment Systems 169
Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations 168
Stand-alone containment analysis of the Phébus FPT-1 test with the ASTEC and the MELCOR codes 167
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 166
Comparison and Analysis of the Condensation Benchmark Results 165
Stand-alone Containment Analysis of four Phébus tests with the ASTEC and MELCOR codes 165
Lithium-Lead/water interaction: LIFUS5/Mod3 series E tests analysed by SIMMER-III coupled with RELAP5 161
The Safety Margins Evaluation in Next Generation of Nuclear Reactors 161
Effects Due to an Obstacle Presence in STARDUST Mobilization Experiments 161
Thermal Hydraulics Analysis of Integrated Blanket ELMS and Divertor Primary Heat Transfer System of ITER Fusion Reactor 161
Bases for Aerosol Resuspension Modelling in the Light of STORM Experiments 160
Comparison report of the OECD/CSNI International Standard Problem 21 (PIPER-ONE experiment SB-7) 160
The European Research on Severe Accidents in Generation 2 and 3 Nuclear Power Plants 159
Stand-alone containment analysis of the Phébus FPT-3 test with the ASTEC and the MELCOR codes 159
Challenges to Computing Buoyancy-Driven Flows in the Containment System of LWRs 158
Il rinascimento nucleare sarà trainato dalla globalizzazione economica? 158
Code accuracy evaluation of ISP 35 calculations based on NUPEC M-7-1 test 157
Status of the TA2/SARNET R&D activities 157
Validation of Severe Accident Codes Against Phebus FP for Plant Applications (PHEBEN2) 155
Vapour Condensation in Presence of Air in the TOSQAN Facility: A Computational Analysis 155
ERMSAR-2017 conference of NUGENIA/SARNET on research on severe accidents in nuclear power plants 154
Stand-alone containment analysis of the Phébus FPT tests with the ASTEC and the MELCOR codes: the FPT-2 test 154
In-Vessel Phase of the Benchmark Exercise on an Alternative TMI-2 Accident Scenario 152
Analysis of the OECD/CSNI ISP No. 46 on the PHEBUS FPT-1 Test Using the ECART 2k Code 152
Bases for Dust Mobilisation Modelling in the Light of STARDUST Experiments 151
Heat and Mass Transfer Models in LWRs Containment Systems 151
Experimental and Computational Analysis of Steam Condensation in the Presence of Air and Helium 151
Evaluation of Containment Heat and Mass Transfer Models with Consideration on the PHEBUS-FP Containment Vessel 151
The 10th European Review Meeting on Severe Accident Research ERMSAR 2022: Severe Accident Research Eleven Years after the Fukushima Accident 151
A new integrated containment system for PWRs, able to mitigate severe accidents 150
MELCOR 2.2 Modelling for Fusion Reactor Analysis 148
The Coupled Phenomenology of Accident Evolution for Primary System and Containment in Innovative LWRs 147
OECD-CSNI Containment Standard Problem N. 3: Calculation Results Using ARIANNA Computer Code 147
An Integrated Approach to the Hydrogen Challenge in the Containment System of Advanced LWRs 146
Modelling Requirements for Source Term Evaluation in Simplified LWRs 142
Towards a decarbonised world 142
Investigation on Gas Distribution Phenomena inside the Containment System of LWRs 141
Coupling between Primary and Secondary Systems in Water Reactors with Passive Safety Features 141
Environmental Source terms during a few Reference Accident Sequences (RAS) of NET/ITER plant 140
Post-test analysis of Series D experiments in LIFUS5/Mod3 facility for SIMMER code validation of WCLL-BB In-box LOCA 140
Uncertainties of Source Term Assessments (USTA): An Indispensable Project 139
Application of AFT Fathom code to steady-state thermal-hydraulics analysis of ITER Primary Heat Transfer Systems 139
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project 138
An Integrated Approach between Primary System and Containment to Evaluate the Source Term in Advanced LWRs 137
Bases for Dust Mobilisation Modelling in the Light of Stardust Experiments 137
Methodologies for the safety analysis of innovative nuclear systems 137
The Problem of the Thermal-hydraulic Transient Inside Full Pressure Containment System Following a LOCA 137
Effects of Spray/Walls Interactions in TOSQAN Tests 136
null 136
The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel 135
Analisi dello stato dell'arte sul coefficiente di scambio termico con vapore in condensazione nei sistemi di contenimento dei reattori nucleari 135
Ex Vessel LOCA Detection for a Primary Heat Transfer System of Fusion Plants 134
DCMN Calculations for the ISP-40 on STORM Test SR-11 Using the ECART Computer Code 134
Analysis of the Ingress of Coolant Event tests performed in the upgraded ICE facility aimed at the ECART code validation 134
Totale 18.344
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Categoria #
all - tutte 127.649
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 127.649
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20223.598 58 257 111 207 745 534 117 182 151 137 218 881
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
2026/2027327 327 0 0 0 0 0 0 0 0 0 0 0
Totale 47.051