ENEA-IRIS Open Archive è l’archivio della produzione scientifica dell'ENEA, realizzato con l'obiettivo di raccogliere, catalogare e rendere facilmente accessibili in rete i risultati della ricerca. Gli autori dell’ENEA provvedono a depositare le proprie pubblicazioni (articoli su rivista, presentazioni a congressi, report, ecc.). In particolare, quelle finanziate dalla Commissione Europea nell’ambito del programma H2020 (che prevede il deposito obbligatorio in un Repository), una volta caricate, vengono automaticamente importate dal portale europeo OpenAIRE. È possibile inserire, o importare direttamente dalle banche dati previste, le informazioni descrittive del documento e anche allegare, ove consentito dalla normativa sul diritto d'autore, il testo completo della pubblicazione.

ENEA-IRIS Open Archive utilizza la piattaforma IRIS (Institutional Research Information System) sviluppata da CINECA.

MASCARI, FULVIO
 Distribuzione geografica
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Continente #
EU - Europa 2.483
NA - Nord America 1.201
AS - Asia 715
SA - Sud America 172
AF - Africa 16
OC - Oceania 5
Continente sconosciuto - Info sul continente non disponibili 1
Totale 4.593
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Nazione #
US - Stati Uniti d'America 1.113
RU - Federazione Russa 1.092
IT - Italia 474
CN - Cina 267
DE - Germania 209
SG - Singapore 208
FR - Francia 172
AT - Austria 162
BR - Brasile 156
GB - Regno Unito 129
HK - Hong Kong 120
SE - Svezia 105
CA - Canada 71
FI - Finlandia 37
NL - Olanda 35
JP - Giappone 32
VN - Vietnam 23
IN - India 21
CZ - Repubblica Ceca 15
BE - Belgio 12
ES - Italia 9
UZ - Uzbekistan 9
IE - Irlanda 7
MX - Messico 7
IR - Iran 6
AR - Argentina 5
DZ - Algeria 5
PL - Polonia 5
UA - Ucraina 5
AU - Australia 4
BD - Bangladesh 4
EC - Ecuador 4
MA - Marocco 4
IQ - Iraq 3
LT - Lituania 3
PA - Panama 3
PK - Pakistan 3
BG - Bulgaria 2
CH - Svizzera 2
CL - Cile 2
CO - Colombia 2
ET - Etiopia 2
GR - Grecia 2
HU - Ungheria 2
IL - Israele 2
JM - Giamaica 2
JO - Giordania 2
KR - Corea 2
KZ - Kazakistan 2
LV - Lettonia 2
MY - Malesia 2
TR - Turchia 2
VE - Venezuela 2
ZA - Sudafrica 2
AE - Emirati Arabi Uniti 1
BH - Bahrain 1
CI - Costa d'Avorio 1
DO - Repubblica Dominicana 1
EU - Europa 1
GT - Guatemala 1
HN - Honduras 1
ID - Indonesia 1
KE - Kenya 1
KG - Kirghizistan 1
LA - Repubblica Popolare Democratica del Laos 1
LK - Sri Lanka 1
NI - Nicaragua 1
NZ - Nuova Zelanda 1
PS - Palestinian Territory 1
PT - Portogallo 1
PY - Paraguay 1
SI - Slovenia 1
SV - El Salvador 1
TN - Tunisia 1
Totale 4.593
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Città #
Chandler 281
Moscow 221
Santa Clara 124
Rome 117
Hong Kong 100
Vienna 94
Boardman 81
Singapore 80
Ashburn 78
Toronto 69
San Mateo 66
Southend 64
Hamburg 63
The Dalles 39
New York 38
Nuremberg 38
Tokyo 29
Beijing 27
Falkenstein 26
Berlin 25
North Bergen 24
Milan 23
Dong Ket 22
Helsinki 22
Miami 21
Shenzhen 19
Los Angeles 18
Palermo 18
Bologna 17
Marseille 15
Xi'an 14
Amsterdam 12
Guangzhou 12
Redwood City 12
Frankfurt am Main 11
Turku 11
Brussels 10
Munich 10
Ann Arbor 9
Turin 9
London 8
Mountain View 8
São Paulo 8
Tashkent 8
Trenton 8
Belo Horizonte 6
Brno 6
Düsseldorf 6
Ningbo 6
Rio de Janeiro 6
Washington 6
Council Bluffs 5
San Francisco 5
Cixi 4
Hangzhou 4
Las Vegas 4
Mexico City 4
Mumbai 4
Paris 4
Shaoxing 4
Shijiazhuang 4
Tappahannock 4
Tehran 4
Uberlândia 4
Zibo 4
Dublin 3
Florence 3
Gueltat Sidi Saad 3
Karlsruhe 3
Mauá 3
Mazzano Romano 3
Napoli 3
Olomouc 3
Prague 3
Rondonópolis 3
Salerno 3
Salvador 3
Seattle 3
Sorocaba 3
Tübingen 3
Venice 3
Viareggio 3
Wroclaw 3
Wuxi 3
Xiamen 3
Amman 2
Angera 2
Baoding 2
Barquisimeto 2
Belford Roxo 2
Blumenau 2
Brisbane 2
Budapest 2
Buffalo 2
Cagliari 2
Campinas 2
Carapicuíba 2
Castellarano 2
Caxias do Sul 2
Charlotte 2
Totale 2.193
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Nome #
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe 172
Description of PERSEO Test n. 7 for International Open Benchmark Exercise 152
In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking 144
Analisi delle temperature nei fondi dei generatori di vapore di reattori frontalieri PWR da 900 MWE in caso di LBLOCA in gamma calda 144
Description of PERSEO test n 7 121
Implementazione su calcolatore parallelo di metodi e codici per le analisi di sensitività ed incertezza nel calcolo di incidenti severi 119
Analysis of nodalization strategies to model a suppression tank for fusion plants with TRACE code 116
Divertor Tokamak Test facility project: status of design and implementation 110
Validation of the trace code against small modular integral reactor natural circulation phenomena 110
Summary of the activities and analyses carried out using USNRC codes 108
Analysis of a Station Black-Out transient in SMR by using the TRACE and RELAP5 code 105
ASTEC - RAVEN coupling for uncertainty analysis of an ingress of coolant event in fusion plants 103
Relazione sulle attività svolte e le analisi effettuate con i codici USNRC 100
Analisi mediante il codice TRACE delle principali fenomenologie caratterizzanti il transitorio conseguente ad una rottura a ghigliottina nella linea DVI dell’impianto sperimentale SPES-3 99
Analyses of the TRACE V5 capability for the simulation of natural circulation and primary/containment coupling in BDBA condition typical of the MASLWR 99
Fukushima Dai-ichi Unit 1 Accident Simulation by Best Estimate and Integral Codes & Accident Management Procedures Identification Focusing on BWR close to the Italian Borders 95
Analisi di transitori non mitigati: perdite di refrigerante da piccola rottura in PWR, perdita d’acqua di alimento del GV in PWR e SBO in BWR 93
Analisi e valutazioni di incidenti severi in LWR 90
Integral Calculations of Severe Accident Scenarios in PWRs and BWRs 90
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis 90
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code 88
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes 88
Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool 87
Integral study of accident sequences with reference to NPPs next to the Italian borders 86
Summary of the activities and analyses carried out using USNRC codes in 2023 79
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 78
Progress in modeling in-containment source term with ASTEC-Na 78
A Bayesian framework of inverse uncertainty quantification with principal component analysis and Kriging for the reliability analysis of passive safety systems 75
null 75
Modifiche del codice RELAP5/MOD3.2.β per lo studio delle perdite di carico e dello scambio termico in condotti elicoidali interessati da deflussi bifase: Validazione attraverso gli esperimenti effettuati dalPolitecnico di Milano presso l’impianto SIET di Piacenza 74
Nodalizzazione MELCOR per lo Studio Integrale di Sequenze Incidentali su Reattori PWR da 900 MWe e valutazioni preliminari d’impatto a breve e medio raggio 72
Summary of the activities and analyses carried out using USNRC CODES in 2022 71
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes 61
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9 60
Current status of MELCOR 2.2 for fusion safety analyses 55
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity 54
BEPU analysis of an Upgraded ICE facility test by TRACE/DAKOTA coupling 52
The EC MUSA project on management and uncertainty of severe accidents: Main pillars and status 51
Application of REPAS to analyze the sump clogging issue following a LOCA and its impact on the reliability of the ECCS long-term core cooling function 51
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project 49
Qualification of RELAP5-3D Code Against the In-pool Passive Energy Removal System PERSEO Data 48
Analyses of the MELCOR Capability to Simulate Integral PWR Using Passive Systems 48
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment 47
Adaptive Sampling Limit Surface Search Application to Identify Cliff-Edge Effects in Severe Accident Uncertainty Analysis 47
Preliminary thermal-hydraulic deterministic safety analysis of an in-vessel LOCA for the DTT facility 47
MELCOR – DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture 45
Nuclear safety Enhanced: A Deep dive into current and future RAVEN applications 43
BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D 43
OECD/NEA/CSNI/WGAMA PERSEO benchmark: Main outcomes and conclusions 43
Small modular reactors and insights on passive mitigation strategy modeling 42
Analysis of unmitigated large break loss of coolant accidents using MELCOR code 41
ASTEC–MAAP Comparison of a 2 Inch Cold Leg LOCA until RPV Failure 40
Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights 40
Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling 40
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes 39
Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review 38
Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions 38
Flow instabilities in helical-coil steam generators for small modular reactors: A review 37
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants 36
Simulation of QUENCH-06 Experiment by MELCOR v2.2 with Uncertainty Analysis 36
OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR) 35
Major Achievements of the EC MUSA Project 34
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package 32
Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool 32
Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code 31
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes 29
Advances in Transient Thermal-Hydraulics in Water Cooled Nuclear Reactors: Main Outcomes of the OECD/NEA Specialist Meeting 27
Severe accident sensitivity and uncertainty estimation using MELCOR and RAVEN 27
Passive safety systems analysis: A novel approach for inverse uncertainty quantification based on Stacked Sparse Autoencoders and Kriging metamodeling 23
Totale 4.752
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Categoria #
all - tutte 20.357
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 20.357
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202015 0 0 0 0 0 0 0 0 0 0 14 1
2020/2021235 1 1 8 5 45 4 8 25 11 18 78 31
2021/2022309 6 72 13 18 22 5 30 57 11 6 35 34
2022/2023737 52 137 39 92 37 127 14 86 109 20 12 12
2023/2024469 29 12 49 16 47 73 35 35 25 22 55 71
2024/20252.936 19 141 25 68 162 25 139 483 390 281 1.203 0
Totale 4.752