CINECA IRIS Institutional Research Information System

ANGELUCCI, MICHELA
 Distribuzione geografica
Salva come PNG Salva come JPEG
Continente #
AS - Asia 1.296
NA - Nord America 1.008
EU - Europa 796
SA - Sud America 368
AF - Africa 36
OC - Oceania 1
Totale 3.505
Salva come PNG Salva come JPEG
Nazione #
US - Stati Uniti d'America 972
SG - Singapore 490
IT - Italia 346
BR - Brasile 303
CN - Cina 277
HK - Hong Kong 219
VN - Vietnam 145
BG - Bulgaria 98
DE - Germania 75
SE - Svezia 52
GB - Regno Unito 46
KR - Corea 46
AR - Argentina 29
FI - Finlandia 28
JP - Giappone 28
RU - Federazione Russa 28
ES - Italia 20
BD - Bangladesh 19
FR - Francia 17
NL - Olanda 17
CA - Canada 16
AT - Austria 15
EC - Ecuador 14
IN - India 14
MX - Messico 13
TR - Turchia 13
ID - Indonesia 12
UA - Ucraina 12
PL - Polonia 11
CZ - Repubblica Ceca 9
MA - Marocco 9
ZA - Sudafrica 9
IQ - Iraq 7
CO - Colombia 6
MO - Macao, regione amministrativa speciale della Cina 6
PE - Perù 5
DZ - Algeria 4
EG - Egitto 4
IE - Irlanda 4
LT - Lituania 4
UY - Uruguay 4
AE - Emirati Arabi Uniti 3
GH - Ghana 3
IL - Israele 3
IR - Iran 3
PT - Portogallo 3
PY - Paraguay 3
SI - Slovenia 3
UZ - Uzbekistan 3
BE - Belgio 2
CI - Costa d'Avorio 2
CL - Cile 2
CR - Costa Rica 2
TN - Tunisia 2
TT - Trinidad e Tobago 2
AZ - Azerbaigian 1
BH - Bahrain 1
BO - Bolivia 1
DK - Danimarca 1
GA - Gabon 1
GE - Georgia 1
GT - Guatemala 1
HN - Honduras 1
HR - Croazia 1
JO - Giordania 1
KE - Kenya 1
MK - Macedonia 1
NG - Nigeria 1
NP - Nepal 1
PK - Pakistan 1
PR - Porto Rico 1
PW - Palau 1
QA - Qatar 1
RO - Romania 1
RS - Serbia 1
SA - Arabia Saudita 1
SK - Slovacchia (Repubblica Slovacca) 1
VE - Venezuela 1
Totale 3.505
Salva come PNG Salva come JPEG
Città #
Singapore 245
Hong Kong 218
Santa Clara 214
Dallas 144
Ashburn 108
Shanghai 95
Sofia 73
Teramo 49
Beijing 47
Ho Chi Minh City 44
Boardman 41
Hefei 41
Pisa 39
Hanoi 37
Milan 37
Los Angeles 35
New York 35
São Paulo 31
London 29
Seoul 27
Serra 26
Princeton 24
Rome 21
Tokyo 21
Falkenstein 20
Lawrence 18
Madrid 15
Munich 15
Pescara 14
Chandler 13
Fairfield 12
Helsinki 12
Wilmington 12
Ancona 11
Genoa 11
Nuremberg 11
Lucca 10
Medford 10
Montesilvano 10
Notaresco 10
Redondo Beach 10
Turku 10
Istanbul 9
Rio de Janeiro 9
San Vito Chietino 9
Vienna 9
Warsaw 9
Boulder 8
Buffalo 8
Ogden 8
San Jose 8
Bellante 7
Casablanca 7
Champaign 7
Council Bluffs 7
Dong Ket 7
Haiphong 7
Houston 7
Montreal 7
Palermo 7
Porto Alegre 7
San Giuliano Terme 7
Denver 6
Guayaquil 6
Jeju City 6
Johannesburg 6
Lappeenranta 6
Martino 6
Orem 6
Stockholm 6
Atlanta 5
Biên Hòa 5
Brasília 5
Brooklyn 5
Chicago 5
Dhaka 5
Frankfurt am Main 5
Tübingen 5
Verona 5
Belo Horizonte 4
Boston 4
Bắc Ninh 4
Campinas 4
Columbus 4
Curitiba 4
Dublin 4
Düsseldorf 4
Elk Grove Village 4
Fortaleza 4
Hải Dương 4
Lima 4
Mexico City 4
Montevideo 4
Nanjing 4
Ottawa 4
Portsmouth 4
Quito 4
Salvador 4
Woodbridge 4
Accra 3
Totale 2.235
Salva come PNG Salva come JPEG
Nome #
First Outcomes from the PHEBUS FPT1 Uncertainty Application done in the EU-MUSA Project 239
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 158
PHEBUS FPT1 Uncertainty Application with the MELCOR 2.2 Code 109
Thermal Characterization of the Nuclear Fuel Stored in a Dry Concrete Cask with the MELCOR Code 104
MUSA WP4 Second Intermediate Reporting 104
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project 104
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture 101
MELCOR/DAKOTA COUPLING IN THE SNAP ENVIRONMENT/ARCHITECTURE 100
The Effect of Backfill Gas Pressure on the Thermal Response of a Dry Cask for Spent Nuclear Fuel 96
Current status of MELCOR 2.2 for fusion safety analyses 96
MUSA – WP4 Intermediate Reporting UNIPI 94
Hybrid neural network and statistical forecasting methodology for predictive monitoring and residual useful life estimation in nuclear power plant components 94
Post-test numerical analysis of a helium-cooled breeding blanket first wall under LOFA conditions with the MELCOR fusion code 90
Uncertainty and Sensitivity Analyses of Source Term Estimates during an Unmitigated SBO Sequence in a PWR-1000 Reactor 80
Comparison of PHEBUS FPT1 uncertainty applications using MELCOR 2.2 with three different methodologies 80
On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions 80
MELCOR/DAKOTA coupling 76
Application of Inverse Uncertainty Quantification in the Severe Accident Domain: Fission Product Release Modelling 75
Thermal analysis of HI-STORM 100S dry cask with the MELCOR code 75
Thermal Characterization of a Dry Storage System for Spent Nuclear Fuel Management 75
Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency 74
Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel 70
CROSS-COMPARISON OF DIFFERENT TECHNIQUES FOR SENSITIVITY ANALYSIS IN SEVERE ACCIDENTS: APPLICATION TO A SBO IN A PWR 69
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 69
Preliminary uncertainty assessment of the containment behavior for the Phebus FPT1 test 69
MUSA WP4 Third Intermediate Reporting 68
HPC modelling for nuclear safety assessment 67
MUSA WP4 Annual Meeting - UNIPI 65
ANALYSIS OF THE DYNAMIC BEHAVIOUR OF A NUCLEAR CONTAINMENT STRUCTURE UNDER MISSILE IMPACT 63
Thermal characterization with the MELCOR code of the nuclear fuel stored in dry concrete casks 63
APPLICATION OF SENSITIVITY ANALYSIS TECHNIQUES TO A LOW DIMENTIONAL PROBLEM IN THE FRAME OF SEVERE ACCIDENTS 57
SOURCE TERM UNCERTAINTIES IN UNMITIGATED SBO SEQUENCES IN A PWR-1000: INSIGHTS FROM THE EU-MUSA PROJECT 55
NEURAL NETWORK-DRIVEN METHODOLOGY FOR PREDICTIVE HEALTH MONITORING AND AGING MANAGEMENT IN NUCLEAR POWER PLANT OPERATIONS 54
null 52
Current status of MELCOR 2.2 for fusion safety analyses 51
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package 50
Supervised Machine Learning-based Feature Selection in the frame of BEPU in Severe Accidents 50
UNCERTAINTIES ON FISSION PRODUCT RELEASE IN A LOSS-OF-COOLING SCENARIO IN A SPENT FUEL POOL WITH MELCOR 2.0 49
Thermal modeling of SNF behavior during dry storage 44
Assessment of Uncertainties Effect on Accident Progression and Fission Product Release in a Spent Fuel Pool 44
Advancing Pool Scrubbing Simulations: from Traditional to AI Methods 38
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application 36
WP2.6: Severe Accident Database Directory (SADD) 35
WP4.3: Review of partners’ uncertainty and sensitivity analysis (UASA) applications 34
Fission Product Release Modeling in MELCOR: an Extension of the Validation 33
On the UaSA Application to the PHEBUS-FPT1 scenario 31
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies 30
CIEMAT's Lessons learned and insights from PHEBUS-FPT1 analysis 29
Inverse Uncertainty Quantification for Severe Accident Analyses 23
Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release 22
EFFECT OF CORIUM PROPERTIES’ UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT 22
UNIPI's Lessons learned and insights from PHEBUS-FPT1 analysis 21
Corium Properties & Accident Scenarios: Preliminary Insights 21
Phenomena Identification and Ranking Table for Containment Phenomena during Severe Accidents in Light Water Reactors 19
Sensitivity analysis in severe accident simulations:A historical perspective 14
Totale 3.621
Salva come PNG Salva come JPEG
Categoria #
all - tutte 10.361
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 10.361
Salva come PNG Salva come JPEG


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021172 0 0 0 0 0 0 1 5 14 111 9 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
2025/20261.378 60 271 278 375 250 144 0 0 0 0 0 0
Totale 3.621