CINECA IRIS Institutional Research Information System

ANGELUCCI, MICHELA
 Distribuzione geografica
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Continente #
AS - Asia 1.613
NA - Nord America 1.577
EU - Europa 1.041
SA - Sud America 395
Continente sconosciuto - Info sul continente non disponibili 130
AF - Africa 41
OC - Oceania 1
Totale 4.798
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Nazione #
US - Stati Uniti d'America 1.511
SG - Singapore 581
IT - Italia 481
CN - Cina 347
BR - Brasile 320
HK - Hong Kong 234
VN - Vietnam 197
BG - Bulgaria 100
DE - Germania 84
SE - Svezia 78
JP - Giappone 61
GB - Regno Unito 52
KR - Corea 52
FR - Francia 47
FI - Finlandia 36
RU - Federazione Russa 32
AR - Argentina 30
BD - Bangladesh 28
ES - Italia 26
CA - Canada 24
NL - Olanda 24
IN - India 23
TR - Turchia 18
AT - Austria 16
MX - Messico 16
ID - Indonesia 15
EC - Ecuador 14
UA - Ucraina 14
PL - Polonia 11
CO - Colombia 10
CZ - Repubblica Ceca 9
MA - Marocco 9
ZA - Sudafrica 9
IQ - Iraq 8
JM - Giamaica 6
MO - Macao, regione amministrativa speciale della Cina 6
PK - Pakistan 6
SI - Slovenia 6
UY - Uruguay 6
DZ - Algeria 5
PE - Perù 5
SA - Arabia Saudita 5
UZ - Uzbekistan 5
AE - Emirati Arabi Uniti 4
EG - Egitto 4
HN - Honduras 4
IE - Irlanda 4
IL - Israele 4
LT - Lituania 4
TN - Tunisia 4
CH - Svizzera 3
CR - Costa Rica 3
GH - Ghana 3
GT - Guatemala 3
IR - Iran 3
KE - Kenya 3
MY - Malesia 3
PT - Portogallo 3
PY - Paraguay 3
VE - Venezuela 3
AZ - Azerbaigian 2
BE - Belgio 2
BH - Bahrain 2
BO - Bolivia 2
CI - Costa d'Avorio 2
CL - Cile 2
JO - Giordania 2
NP - Nepal 2
PR - Porto Rico 2
RO - Romania 2
TT - Trinidad e Tobago 2
AG - Antigua e Barbuda 1
BZ - Belize 1
DK - Danimarca 1
EE - Estonia 1
GA - Gabon 1
GD - Grenada 1
GE - Georgia 1
GP - Guadalupe 1
HR - Croazia 1
LB - Libano 1
MK - Macedonia 1
MT - Malta 1
NG - Nigeria 1
OM - Oman 1
PW - Palau 1
QA - Qatar 1
RS - Serbia 1
SK - Slovacchia (Repubblica Slovacca) 1
SV - El Salvador 1
TC - Turks e Caicos 1
TH - Thailandia 1
Totale 4.668
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Città #
Singapore 309
Hong Kong 227
Santa Clara 221
San Jose 184
Ashburn 169
Dallas 148
Shanghai 95
Sofia 75
Milan 67
Ho Chi Minh City 60
Columbus 54
Hanoi 54
Beijing 53
Tokyo 51
Teramo 49
Los Angeles 48
Pisa 45
Boardman 41
Hefei 41
New York 37
São Paulo 36
Council Bluffs 34
London 30
Rome 30
Seoul 27
Serra 26
Lauterbourg 25
Princeton 24
Falkenstein 20
Helsinki 19
Lawrence 18
Genoa 16
Madrid 16
Baltimore 15
Munich 15
Pescara 14
Chandler 13
Ancona 12
Fairfield 12
Turin 12
Wilmington 12
Buffalo 11
Houston 11
Istanbul 11
Nuremberg 11
Lucca 10
Medford 10
Montesilvano 10
Montreal 10
Notaresco 10
Orem 10
Redondo Beach 10
Turku 10
Frankfurt am Main 9
Haiphong 9
Palermo 9
Rio de Janeiro 9
San Vito Chietino 9
Vienna 9
Warsaw 9
Atlanta 8
Boulder 8
Brooklyn 8
Champaign 8
Chicago 8
Lacchiarella 8
Ogden 8
Bellante 7
Casablanca 7
Denver 7
Dhaka 7
Dong Ket 7
Lappeenranta 7
Phoenix 7
Porto Alegre 7
San Giuliano Terme 7
Biên Hòa 6
Guayaquil 6
Jeju City 6
Johannesburg 6
Karlsruhe 6
Martino 6
Stockholm 6
Verona 6
Belo Horizonte 5
Brasília 5
Campinas 5
Chennai 5
Figino 5
Montevideo 5
Tashkent 5
Tübingen 5
Amsterdam 4
Bogotá 4
Boston 4
Bắc Ninh 4
Curitiba 4
Dublin 4
Düsseldorf 4
Elk Grove Village 4
Totale 2.880
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Nome #
First Outcomes from the PHEBUS FPT1 Uncertainty Application done in the EU-MUSA Project 263
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 168
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project 140
The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel 136
Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components 135
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture 131
MUSA WP4 Second Intermediate Reporting 128
PHEBUS FPT1 Uncertainty Application with the MELCOR 2.2 Code 128
Current status of MELCOR 2.2 for fusion safety analyses 120
Thermal Characterization of the Nuclear Fuel Stored in a Dry Concrete Cask with the MELCOR Code 118
MUSA – WP4 Intermediate Reporting UNIPI 118
MELCOR/DAKOTA COUPLING IN THE SNAP ENVIRONMENT/ARCHITECTURE 108
Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency 104
Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel 103
Uncertainty and Sensitivity Analyses of Source Term Estimates during an Unmitigated SBO Sequence in a PWR-1000 Reactor 102
HPC modelling for nuclear safety assessment 99
Post-test numerical analysis of a helium-cooled breeding blanket first wall under LOFA conditions with the MELCOR fusion code 99
ANALYSIS OF THE DYNAMIC BEHAVIOUR OF A NUCLEAR CONTAINMENT STRUCTURE UNDER MISSILE IMPACT 94
APPLICATION OF SENSITIVITY ANALYSIS TECHNIQUES TO A LOW DIMENTIONAL PROBLEM IN THE FRAME OF SEVERE ACCIDENTS 91
Comparison of PHEBUS FPT1 uncertainty applications using MELCOR 2.2 with three different methodologies 91
On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions 91
Application of Inverse Uncertainty Quantification in the Severe Accident Domain: Fission Product Release Modelling 90
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 87
MELCOR/DAKOTA coupling 84
Thermal Characterization of a Dry Storage System for Spent Nuclear Fuel Management 83
Preliminary uncertainty assessment of the containment behavior for the Phebus FPT1 test 83
CROSS-COMPARISON OF DIFFERENT TECHNIQUES FOR SENSITIVITY ANALYSIS IN SEVERE ACCIDENTS: APPLICATION TO A SBO IN A PWR 82
Best-estimate for system codes (Besyc): A new software to perform best-estimate plus uncertainty analyses with thermal-hydraulic and safety system codes for both fusion and fission scenarios 82
NEURAL NETWORK-DRIVEN METHODOLOGY FOR PREDICTIVE HEALTH MONITORING AND AGING MANAGEMENT IN NUCLEAR POWER PLANT OPERATIONS 80
Thermal characterization with the MELCOR code of the nuclear fuel stored in dry concrete casks 80
MUSA WP4 Annual Meeting - UNIPI 73
MUSA WP4 Third Intermediate Reporting 72
SOURCE TERM UNCERTAINTIES IN UNMITIGATED SBO SEQUENCES IN A PWR-1000: INSIGHTS FROM THE EU-MUSA PROJECT 71
Supervised Machine Learning-based Feature Selection in the frame of BEPU in Severe Accidents 66
Advancing Pool Scrubbing Simulations: from Traditional to AI Methods 64
Fission Product Release Modeling in MELCOR: an Extension of the Validation 64
Current status of MELCOR 2.2 for fusion safety analyses 64
UNCERTAINTIES ON FISSION PRODUCT RELEASE IN A LOSS-OF-COOLING SCENARIO IN A SPENT FUEL POOL WITH MELCOR 2.0 62
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package 61
Thermal modeling of SNF behavior during dry storage 61
EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT 60
null 52
Phenomena Identification and Ranking Table for Containment Phenomena during Severe Accidents in Light Water Reactors 51
Assessment of Uncertainties Effect on Accident Progression and Fission Product Release in a Spent Fuel Pool 51
Inverse Uncertainty Quantification for Severe Accident Analyses 50
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application 49
Sensitivity analysis in severe accident simulations:A historical perspective 45
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release 44
WP4.3: Review of partners’ uncertainty and sensitivity analysis (UASA) applications 38
WP2.6: Severe Accident Database Directory (SADD) 38
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies 38
Corium Properties & Accident Scenarios: Preliminary Insights 37
INTEGRATED SEVERE ACCIDENT ANALYSIS FOR A VVER-1000: ACCIDENT PROGRESSION, UNCERTAINTY QUANTIFICATION, AND RADIOLOGICAL CONSEQUENCES 36
CIEMAT's Lessons learned and insights from PHEBUS-FPT1 analysis 35
On the UaSA Application to the PHEBUS-FPT1 scenario 32
Assessing the Capabilities of MELCOR V2.2 against the QUENCH-19 Bundle Test with FeCrAl Cladding 30
Impact of FeCrAl Cladding Material on the Progression of a Severe Accident in a Generic BWR Mark-I NPP: analysis of a SBO Scenario with the ASTEC Code 27
EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT 26
UNIPI's Lessons learned and insights from PHEBUS-FPT1 analysis 24
ASSESSMENT OF POOL SCRUBBING PREDICTIVE CAPABILITIES: BENCHMARKING SPARC90 AGAINST AN AD-HOC DATABASE 24
Techniques for Sensitivity Analysis in Severe Accidents: A Comparative Study 24
Validation database for pool scrubbing: an update 11
Totale 4.798
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Categoria #
all - tutte 13.739
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 13.739
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/2022233 0 6 13 8 25 15 11 50 18 18 21 48
2022/2023153 31 8 26 8 12 25 14 8 9 2 1 9
2023/2024273 14 15 37 11 52 26 43 12 6 6 16 35
2024/20251.389 3 36 92 35 142 161 112 94 147 188 162 217
2025/20262.372 60 271 278 375 250 149 286 86 134 140 123 220
2026/2027183 111 72 0 0 0 0 0 0 0 0 0 0
Totale 4.798