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 4.241
NA - Nord America 1.890
AS - Asia 1.247
SA - Sud America 272
AF - Africa 19
Continente sconosciuto - Info sul continente non disponibili 11
OC - Oceania 6
Totale 7.686
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Nazione #
RU - Federazione Russa 2.873
US - Stati Uniti d'America 1.716
SG - Singapore 574
DE - Germania 462
GB - Regno Unito 283
BR - Brasile 248
HK - Hong Kong 239
SE - Svezia 222
CN - Cina 209
IT - Italia 197
CA - Canada 154
FR - Francia 78
JP - Giappone 65
KR - Corea 60
AT - Austria 39
IN - India 30
FI - Finlandia 29
BE - Belgio 18
IQ - Iraq 13
VN - Vietnam 13
MX - Messico 12
EU - Europa 11
NL - Olanda 10
BD - Bangladesh 9
CZ - Repubblica Ceca 8
TR - Turchia 8
AR - Argentina 7
UZ - Uzbekistan 7
IR - Iran 6
AU - Australia 5
CO - Colombia 5
DZ - Algeria 5
EC - Ecuador 5
PK - Pakistan 5
ZA - Sudafrica 5
ES - Italia 4
PL - Polonia 4
TN - Tunisia 4
UA - Ucraina 4
GR - Grecia 3
LT - Lituania 3
BB - Barbados 2
CL - Cile 2
DO - Repubblica Dominicana 2
ET - Etiopia 2
SA - Arabia Saudita 2
VE - Venezuela 2
AL - Albania 1
BH - Bahrain 1
CI - Costa d'Avorio 1
CR - Costa Rica 1
GE - Georgia 1
GT - Guatemala 1
HN - Honduras 1
JO - Giordania 1
KE - Kenya 1
LB - Libano 1
LK - Sri Lanka 1
MA - Marocco 1
MY - Malesia 1
NP - Nepal 1
NZ - Nuova Zelanda 1
PA - Panama 1
PE - Perù 1
PT - Portogallo 1
PY - Paraguay 1
RS - Serbia 1
SI - Slovenia 1
UY - Uruguay 1
Totale 7.686
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Città #
Moscow 683
Chandler 506
Hamburg 261
Singapore 236
Santa Clara 167
Southend 153
San Mateo 151
Toronto 148
Boardman 129
Hong Kong 124
Ashburn 99
New York 84
Rome 59
Beijing 58
Seoul 57
Berlin 52
Munich 34
The Dalles 32
Falkenstein 26
Columbus 25
Nuremberg 25
Vienna 25
Las Vegas 24
Ann Arbor 23
Marseille 21
Washington 21
Helsinki 20
Brussels 18
Trenton 18
Bologna 17
Los Angeles 15
Belo Horizonte 14
Miami 14
Mountain View 14
Redwood City 14
São Paulo 14
Frankfurt am Main 12
Palermo 12
Tong 12
Jülich 9
Rio de Janeiro 9
Turku 9
Council Bluffs 7
Dong Ket 7
Guangzhou 7
Tashkent 7
Baghdad 6
Curitiba 6
Gif-sur-yvette 6
London 6
Mazzano Romano 6
Paris 6
Shanghai 6
Tokyo 6
Boston 5
Brno 5
Milan 5
Wilmington 5
Atlanta 4
Borås 4
Düsseldorf 4
Guayaquil 4
Juiz de Fora 4
Lauterbourg 4
North Bergen 4
Redmond 4
Rockville 4
San Francisco 4
San Vito Lo Capo 4
Serra 4
Shenzhen 4
Tehran 4
Belford Roxo 3
Bochum 3
Brasília 3
Brooklyn 3
Chennai 3
Como 3
Dallas 3
Dongguan 3
Florence 3
Gueltat Sidi Saad 3
Ho Chi Minh City 3
Mumbai 3
Napoli 3
Olomouc 3
Passos 3
Pisa 3
Warsaw 3
Addis Ababa 2
Amsterdam 2
Angera 2
Ankara 2
Anápolis 2
Bangalore 2
Baoding 2
Bexley 2
Buffalo 2
Campo Grande 2
Caraguatatuba 2
Totale 3.669
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Nome #
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes 352
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment 348
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe 222
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi 189
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants 173
ENEA activity in CESAM Project 166
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes 164
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes 158
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 149
Synthesis of spent fuel pool accident assessments using severe accident codes 148
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling 148
DRACCAR code validation against the ballooned cluster experiment A2R038 of the ACHILLES experimental program 148
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 147
ENEA Activities in the First 6 Months of 1998 142
DRACCAR code validation against unballooned cluster ACHILLES experiments 141
Calculs complémentaires DRACCAR-2 en soutien à la préparation des essais TAGINE sur le réacteur BR2 140
ENEA Activities in the Last 6 Months of 1998 139
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code 137
PHEBUS FPT3: Preliminary Investigation for Designing a Bundle with a B4C Rod 136
Investigation of Core Degradation (COBE). Final Report 134
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code 133
ICARE V3 Mod0 Code Validation against MP-1 Experiment 131
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 128
Investigation of Core Degradation 127
ICARE2 V3 Mod0 Validation against DC1 Experiment 127
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 126
Synthesis of the current understanding of the PHEBUS FP FPT2 test based on the ICARE2 code calculations 126
Exploratory ICARE 2 Calculations for the PHEBUS FPT2 Test (Bundle Aspect) 124
Investigation of Core Degradation (COBE) 121
PHEBUS FPT4: Epaisseur Dissoute et Reponse Thermique Associé du Boitier 120
Post Test Analysis of PHEBUS FPTO Degradation Using the ICARE2 Debris Bed Model 119
Synthesis of IPSN Pre-Test Analysis for FPT0, the First Test of the PHEBUS FP Programme 119
PHEBUS FPT4. First Post Test Calculation on the Debris Bed Using the ICARE2 V3 Code 116
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison 115
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi 114
PHEBUS FPT4: Progression Axial du Bain Fondu 113
PHEBUS FPT4: Sensitivity Calculation to the Debris Bed Relocation Temperature (2573 K) 112
PHEBUS FPT4: Pre-Test Calculation for the Debris Bed Using the ICARE2V3mod0 Code (as of September 1997), JC Crestia 112
New ICARE 2 Calculations and Sensitivity Studies for the FPT0 Test Piloting 110
Survey on FPT-3 Objectives and Pre-Test Analyses 110
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes 110
Preliminary assessment of the DRACCAR thermo-hydraulic module. Comparison with CATHARE2 results on the simulation of a LOCA in a French PWR 109
PHEBUS FPT4: Expected Behaviour during the Melt Progression Phase. Gas Chimney Simulation with ICARE2 V3 Mod0 108
PHEBUS FPT4: Scenario Alternatif: Gonflement du Combustible 107
PHEBUS FPT4: Pressure Drop across the Debris Bed 106
PHEBUS FPT4: Minimum Cross Section of the Steam Chimney 105
PHEBUS FPT4: Aternative Scenarios: Steam Bypass through the Shroud 105
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test 103
Test of DRACCAR thermo-mechanical models on a Loss of coolant accident (LOCA) in Pressurized Water Reactors (PWrs), simulation. Comparison with CATHARE2 results 102
PHEBUS FPT2: Alternative Scenario: Sudden Debris Bed Formation. ICARE2 V3 Mod0 Calculation 101
PHEBUS FPT4: Alternative Scenario: Steam Bypass through the Shroud 101
PHEBUS FPT0 Post-test Analyses: Status of the Bundle Analysis Using ICARE/U2-MOD1 Code 99
PHEBUS FPT3: Preliminary Model for the B4C Oxidation by Steam. Exploratory Calculations using ICARE2 Code. Proposals for the Test Scenario 97
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment 96
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes 87
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 85
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 78
null 75
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes 60
Totale 7.718
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Categoria #
all - tutte 35.260
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 35.260
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021361 0 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
2024/20254.359 11 142 33 49 226 165 115 180 322 161 1.277 1.678
2025/2026654 455 199 0 0 0 0 0 0 0 0 0 0
Totale 7.718