CINECA IRIS Institutional Research Information System

ANGELUCCI, MICHELA
 Distribuzione geografica
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Continente #
AS - Asia 1.600
NA - Nord America 1.454
EU - Europa 997
SA - Sud America 385
AF - Africa 41
OC - Oceania 1
Totale 4.478
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Nazione #
US - Stati Uniti d'America 1.400
SG - Singapore 580
IT - Italia 471
CN - Cina 344
BR - Brasile 315
HK - Hong Kong 231
VN - Vietnam 196
BG - Bulgaria 100
DE - Germania 80
JP - Giappone 60
SE - Svezia 54
GB - Regno Unito 52
KR - Corea 51
FR - Francia 46
FI - Finlandia 36
RU - Federazione Russa 32
AR - Argentina 30
BD - Bangladesh 27
ES - Italia 25
CA - Canada 22
IN - India 22
NL - Olanda 22
TR - Turchia 18
AT - Austria 16
MX - Messico 16
EC - Ecuador 14
ID - Indonesia 14
UA - Ucraina 14
PL - Polonia 11
CZ - Repubblica Ceca 9
MA - Marocco 9
ZA - Sudafrica 9
IQ - Iraq 8
CO - Colombia 6
MO - Macao, regione amministrativa speciale della Cina 6
PK - Pakistan 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
IE - Irlanda 4
IL - Israele 4
LT - Lituania 4
SI - Slovenia 4
TN - Tunisia 4
CH - Svizzera 3
CR - Costa Rica 3
GH - Ghana 3
HN - Honduras 3
IR - Iran 3
JM - Giamaica 3
KE - Kenya 3
MY - Malesia 3
PT - Portogallo 3
PY - Paraguay 3
AZ - Azerbaigian 2
BE - Belgio 2
BH - Bahrain 2
BO - Bolivia 2
CI - Costa d'Avorio 2
CL - Cile 2
GT - Guatemala 2
JO - Giordania 2
NP - Nepal 2
PR - Porto Rico 2
RO - Romania 2
TT - Trinidad e Tobago 2
VE - Venezuela 2
DK - Danimarca 1
EE - Estonia 1
GA - Gabon 1
GD - Grenada 1
GE - Georgia 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
TH - Thailandia 1
Totale 4.478
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Città #
Singapore 308
Hong Kong 226
Santa Clara 220
San Jose 180
Ashburn 148
Dallas 147
Shanghai 95
Sofia 75
Milan 64
Ho Chi Minh City 60
Columbus 54
Hanoi 54
Beijing 52
Tokyo 51
Teramo 49
Pisa 44
Los Angeles 42
Boardman 41
Hefei 41
New York 37
São Paulo 33
London 30
Rome 29
Seoul 27
Serra 26
Lauterbourg 25
Princeton 24
Falkenstein 20
Helsinki 19
Council Bluffs 18
Lawrence 18
Genoa 16
Madrid 16
Munich 15
Baltimore 14
Pescara 14
Chandler 13
Ancona 12
Fairfield 12
Wilmington 12
Istanbul 11
Nuremberg 11
Houston 10
Lucca 10
Medford 10
Montesilvano 10
Montreal 10
Notaresco 10
Orem 10
Redondo Beach 10
Turin 10
Turku 10
Frankfurt am Main 9
Haiphong 9
Palermo 9
Rio de Janeiro 9
San Vito Chietino 9
Vienna 9
Warsaw 9
Boulder 8
Brooklyn 8
Buffalo 8
Champaign 8
Lacchiarella 8
Ogden 8
Atlanta 7
Bellante 7
Casablanca 7
Chicago 7
Denver 7
Dhaka 7
Dong Ket 7
Lappeenranta 7
Porto Alegre 7
San Giuliano Terme 7
Biên Hòa 6
Guayaquil 6
Jeju City 6
Johannesburg 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
Boston 4
Bắc Ninh 4
Curitiba 4
Dublin 4
Düsseldorf 4
Elk Grove Village 4
Fortaleza 4
Grenoble 4
Hải Dương 4
Totale 2.806
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Nome #
First Outcomes from the PHEBUS FPT1 Uncertainty Application done in the EU-MUSA Project 253
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 165
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project 137
The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel 133
Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components 131
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture 127
MUSA WP4 Second Intermediate Reporting 123
PHEBUS FPT1 Uncertainty Application with the MELCOR 2.2 Code 121
Current status of MELCOR 2.2 for fusion safety analyses 118
Thermal Characterization of the Nuclear Fuel Stored in a Dry Concrete Cask with the MELCOR Code 115
MUSA – WP4 Intermediate Reporting UNIPI 112
MELCOR/DAKOTA COUPLING IN THE SNAP ENVIRONMENT/ARCHITECTURE 108
Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency 101
Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel 101
Uncertainty and Sensitivity Analyses of Source Term Estimates during an Unmitigated SBO Sequence in a PWR-1000 Reactor 97
Post-test numerical analysis of a helium-cooled breeding blanket first wall under LOFA conditions with the MELCOR fusion code 97
HPC modelling for nuclear safety assessment 96
ANALYSIS OF THE DYNAMIC BEHAVIOUR OF A NUCLEAR CONTAINMENT STRUCTURE UNDER MISSILE IMPACT 90
Comparison of PHEBUS FPT1 uncertainty applications using MELCOR 2.2 with three different methodologies 89
Application of Inverse Uncertainty Quantification in the Severe Accident Domain: Fission Product Release Modelling 88
APPLICATION OF SENSITIVITY ANALYSIS TECHNIQUES TO A LOW DIMENTIONAL PROBLEM IN THE FRAME OF SEVERE ACCIDENTS 88
On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions 87
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 83
MELCOR/DAKOTA coupling 82
Preliminary uncertainty assessment of the containment behavior for the Phebus FPT1 test 82
Thermal Characterization of a Dry Storage System for Spent Nuclear Fuel Management 81
CROSS-COMPARISON OF DIFFERENT TECHNIQUES FOR SENSITIVITY ANALYSIS IN SEVERE ACCIDENTS: APPLICATION TO A SBO IN A PWR 79
NEURAL NETWORK-DRIVEN METHODOLOGY FOR PREDICTIVE HEALTH MONITORING AND AGING MANAGEMENT IN NUCLEAR POWER PLANT OPERATIONS 79
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 78
Thermal characterization with the MELCOR code of the nuclear fuel stored in dry concrete casks 77
MUSA WP4 Annual Meeting - UNIPI 72
MUSA WP4 Third Intermediate Reporting 71
SOURCE TERM UNCERTAINTIES IN UNMITIGATED SBO SEQUENCES IN A PWR-1000: INSIGHTS FROM THE EU-MUSA PROJECT 70
Supervised Machine Learning-based Feature Selection in the frame of BEPU in Severe Accidents 65
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
Thermal modeling of SNF behavior during dry storage 60
Fission Product Release Modeling in MELCOR: an Extension of the Validation 59
Advancing Pool Scrubbing Simulations: from Traditional to AI Methods 57
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package 57
EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT 54
null 52
Assessment of Uncertainties Effect on Accident Progression and Fission Product Release in a Spent Fuel Pool 49
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application 48
Phenomena Identification and Ranking Table for Containment Phenomena during Severe Accidents in Light Water Reactors 46
Inverse Uncertainty Quantification for Severe Accident Analyses 43
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release 40
Sensitivity analysis in severe accident simulations:A historical perspective 40
WP4.3: Review of partners’ uncertainty and sensitivity analysis (UASA) applications 38
WP2.6: Severe Accident Database Directory (SADD) 37
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies 37
Corium Properties & Accident Scenarios: Preliminary Insights 34
CIEMAT's Lessons learned and insights from PHEBUS-FPT1 analysis 34
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 27
UNIPI's Lessons learned and insights from PHEBUS-FPT1 analysis 24
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 24
INTEGRATED SEVERE ACCIDENT ANALYSIS FOR A VVER-1000: ACCIDENT PROGRESSION, UNCERTAINTY QUANTIFICATION, AND RADIOLOGICAL CONSEQUENCES 22
EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT 21
ASSESSMENT OF POOL SCRUBBING PREDICTIVE CAPABILITIES: BENCHMARKING SPARC90 AGAINST AN AD-HOC DATABASE 20
Techniques for Sensitivity Analysis in Severe Accidents: A Comparative Study 19
Validation database for pool scrubbing: an update 8
Totale 4.604
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Categoria #
all - tutte 12.703
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 12.703
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202132 0 0 0 0 0 0 0 0 0 0 0 32
2021/2022235 2 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
2025/20262.361 60 271 278 375 250 149 286 86 134 140 123 209
Totale 4.604