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.

EDERLI, STEFANO
 Distribuzione geografica
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Continente #
EU - Europa 3.091
NA - Nord America 1.793
AS - Asia 821
SA - Sud America 241
AF - Africa 15
Continente sconosciuto - Info sul continente non disponibili 11
OC - Oceania 6
Totale 5.978
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Nazione #
RU - Federazione Russa 1.774
US - Stati Uniti d'America 1.625
DE - Germania 436
GB - Regno Unito 273
SG - Singapore 255
HK - Hong Kong 239
SE - Svezia 221
BR - Brasile 220
IT - Italia 194
CN - Cina 183
CA - Canada 152
FR - Francia 72
JP - Giappone 64
AT - Austria 39
FI - Finlandia 26
IN - India 26
BE - Belgio 18
EU - Europa 11
IQ - Iraq 10
NL - Olanda 10
VN - Vietnam 10
MX - Messico 9
CZ - Repubblica Ceca 8
UZ - Uzbekistan 7
AR - Argentina 6
IR - Iran 6
AU - Australia 5
CO - Colombia 5
DZ - Algeria 5
EC - Ecuador 5
BD - Bangladesh 4
ES - Italia 4
KR - Corea 4
TN - Tunisia 4
TR - Turchia 4
UA - Ucraina 4
GR - Grecia 3
LT - Lituania 3
PK - Pakistan 3
BB - Barbados 2
CL - Cile 2
PL - Polonia 2
ZA - Sudafrica 2
AL - Albania 1
BH - Bahrain 1
CI - Costa d'Avorio 1
CR - Costa Rica 1
DO - Repubblica Dominicana 1
ET - Etiopia 1
GE - Georgia 1
GT - Guatemala 1
HN - Honduras 1
JO - Giordania 1
KE - Kenya 1
LK - Sri Lanka 1
MA - Marocco 1
MY - Malesia 1
NZ - Nuova Zelanda 1
PA - Panama 1
PE - Perù 1
PT - Portogallo 1
RS - Serbia 1
SA - Arabia Saudita 1
SI - Slovenia 1
UY - Uruguay 1
VE - Venezuela 1
Totale 5.978
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Città #
Moscow 554
Chandler 506
Hamburg 261
Santa Clara 164
Southend 153
San Mateo 151
Toronto 148
Boardman 129
Hong Kong 124
Singapore 96
Ashburn 94
New York 82
Rome 59
Berlin 52
Beijing 32
The Dalles 32
Falkenstein 26
Vienna 25
Las Vegas 24
Nuremberg 24
Ann Arbor 23
Marseille 21
Washington 21
Helsinki 20
Brussels 18
Munich 18
Trenton 18
Bologna 17
Los Angeles 14
Mountain View 14
Redwood City 14
Belo Horizonte 13
Miami 13
Frankfurt am Main 12
Palermo 12
Tong 12
São Paulo 11
Dong Ket 7
Guangzhou 7
Rio de Janeiro 7
Tashkent 7
Curitiba 6
Gif-sur-yvette 6
Mazzano Romano 6
Shanghai 6
Turku 6
Brno 5
Tokyo 5
Wilmington 5
Atlanta 4
Baghdad 4
Borås 4
Düsseldorf 4
Guayaquil 4
Juiz de Fora 4
Lauterbourg 4
London 4
Milan 4
North Bergen 4
Redmond 4
Rockville 4
San Vito Lo Capo 4
Serra 4
Shenzhen 4
Tehran 4
Belford Roxo 3
Bochum 3
Boston 3
Chennai 3
Como 3
Dongguan 3
Florence 3
Gueltat Sidi Saad 3
Napoli 3
Olomouc 3
Passos 3
Pisa 3
San Francisco 3
Amsterdam 2
Angera 2
Anápolis 2
Bangalore 2
Baoding 2
Bexley 2
Brasília 2
Brooklyn 2
Buffalo 2
Campo Grande 2
Caraguatatuba 2
Carapicuíba 2
Cincinnati 2
Cixi 2
Council Bluffs 2
Dallas 2
Embu das Artes 2
Falls Church 2
Goiânia 2
Hanoi 2
Heraklion 2
Itajubá 2
Totale 3.227
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Nome #
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes 315
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment 300
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe 190
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi 152
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants 138
ENEA activity in CESAM Project 132
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes 131
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes 130
Synthesis of spent fuel pool accident assessments using severe accident codes 120
DRACCAR code validation against the ballooned cluster experiment A2R038 of the ACHILLES experimental program 120
Analysis of the ZrO2 Layer Chemical Stability in Zry Cladding above Zry Melting Point. Definition and Validation of a ZrO2 Failure Criterion to be Implemented in the Core Degradation Codes 115
PHEBUS FPT3: Preliminary Investigation for Designing a Bundle with a B4C Rod 115
ENEA Activities in the First 6 Months of 1998 114
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling 114
Assessment of PWR cores behavior and estimate of confidence level got with the use of mechanistic and / or integral codes calculations of accident sequences with reference to TMI-2 reactor 114
DRACCAR code validation against unballooned cluster ACHILLES experiments 113
ENEA Activities in the Last 6 Months of 1998 108
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code 106
ICARE V3 Mod0 Code Validation against MP-1 Experiment 105
Analysis of PBF SFD 1-4 TEST with ICARE2 V2 Mod1 code. Application of a New Criterion for the Cladding External Layer Failure beyond the Zircaloy Melting 104
Calculs complémentaires DRACCAR-2 en soutien à la préparation des essais TAGINE sur le réacteur BR2 104
Investigation of Core Degradation (COBE). Final Report 103
ICARE2 V3 Mod0 Validation against DC1 Experiment 98
Synthesis of the current understanding of the PHEBUS FP FPT2 test based on the ICARE2 code calculations 98
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 96
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code 96
Investigation of Core Degradation 95
Post Test Analysis of PHEBUS FPTO Degradation Using the ICARE2 Debris Bed Model 95
PHEBUS FPT4: Epaisseur Dissoute et Reponse Thermique Associé du Boitier 92
Exploratory ICARE 2 Calculations for the PHEBUS FPT2 Test (Bundle Aspect) 92
Investigation of Core Degradation (COBE) 90
PHEBUS FPT4. First Post Test Calculation on the Debris Bed Using the ICARE2 V3 Code 89
Synthesis of IPSN Pre-Test Analysis for FPT0, the First Test of the PHEBUS FP Programme 89
PHEBUS FPT4: Progression Axial du Bain Fondu 86
PHEBUS FPT4: Pre-Test Calculation for the Debris Bed Using the ICARE2V3mod0 Code (as of September 1997), JC Crestia 85
PHEBUS FPT4: Minimum Cross Section of the Steam Chimney 85
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi 85
PHEBUS FPT4: Pressure Drop across the Debris Bed 83
New ICARE 2 Calculations and Sensitivity Studies for the FPT0 Test Piloting 83
PHEBUS FPT4: Expected Behaviour during the Melt Progression Phase. Gas Chimney Simulation with ICARE2 V3 Mod0 83
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison 83
Survey on FPT-3 Objectives and Pre-Test Analyses 83
PHEBUS FPT4: Sensitivity Calculation to the Debris Bed Relocation Temperature (2573 K) 82
Preliminary assessment of the DRACCAR thermo-hydraulic module. Comparison with CATHARE2 results on the simulation of a LOCA in a French PWR 81
PHEBUS FPT2: Alternative Scenario: Sudden Debris Bed Formation. ICARE2 V3 Mod0 Calculation 79
PHEBUS FPT4: Scenario Alternatif: Gonflement du Combustible 78
PHEBUS FPT4: Alternative Scenario: Steam Bypass through the Shroud 78
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test 76
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes 76
PHEBUS FPT4: Aternative Scenarios: Steam Bypass through the Shroud 75
null 75
PHEBUS FPT0 Post-test Analyses: Status of the Bundle Analysis Using ICARE/U2-MOD1 Code 73
PHEBUS FPT3: Preliminary Model for the B4C Oxidation by Steam. Exploratory Calculations using ICARE2 Code. Proposals for the Test Scenario 73
Test of DRACCAR thermo-mechanical models on a Loss of coolant accident (LOCA) in Pressurized Water Reactors (PWrs), simulation. Comparison with CATHARE2 results 71
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment 64
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 55
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes 54
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 48
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes 43
Totale 6.010
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Categoria #
all - tutte 31.674
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 31.674
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20206 0 0 0 0 0 0 0 0 0 0 0 6
2020/2021366 5 0 1 1 100 8 4 42 24 19 149 13
2021/2022541 21 153 21 26 67 8 28 120 7 6 34 50
2022/20231.067 69 206 75 132 47 162 5 89 233 17 17 15
2023/2024690 40 21 77 13 58 127 22 42 90 48 73 79
2024/20253.305 11 142 33 49 226 165 115 180 322 161 1.277 624
Totale 6.010