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 4.019
NA - Nord America 1.816
AS - Asia 904
SA - Sud America 242
AF - Africa 15
Continente sconosciuto - Info sul continente non disponibili 11
OC - Oceania 6
Totale 7.013
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Nazione #
RU - Federazione Russa 2.688
US - Stati Uniti d'America 1.648
DE - Germania 444
SG - Singapore 337
GB - Regno Unito 274
HK - Hong Kong 239
BR - Brasile 221
SE - Svezia 221
IT - Italia 195
CN - Cina 183
CA - Canada 152
FR - Francia 72
JP - Giappone 64
AT - Austria 39
FI - Finlandia 29
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
BD - Bangladesh 5
CO - Colombia 5
DZ - Algeria 5
EC - Ecuador 5
ES - Italia 4
KR - Corea 4
TN - Tunisia 4
TR - Turchia 4
UA - Ucraina 4
GR - Grecia 3
LT - Lituania 3
PK - Pakistan 3
PL - Polonia 3
BB - Barbados 2
CL - Cile 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 7.013
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Città #
Moscow 683
Chandler 506
Hamburg 261
Singapore 177
Santa Clara 164
Southend 153
San Mateo 151
Toronto 148
Boardman 129
Hong Kong 124
Ashburn 95
New York 82
Rome 59
Berlin 52
Beijing 32
The Dalles 32
Falkenstein 26
Munich 26
Vienna 25
Las Vegas 24
Nuremberg 24
Ann Arbor 23
Marseille 21
Washington 21
Helsinki 20
Brussels 18
Trenton 18
Bologna 17
Los Angeles 14
Mountain View 14
Redwood City 14
Belo Horizonte 13
Columbus 13
Miami 13
Frankfurt am Main 12
Palermo 12
São Paulo 12
Tong 12
Turku 9
Dong Ket 7
Guangzhou 7
Rio de Janeiro 7
Tashkent 7
Curitiba 6
Gif-sur-yvette 6
Mazzano Romano 6
Shanghai 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
Totale 3.461
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Nome #
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes 336
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment 323
Analyses with MELCOR code of an unmitigated SBO scenario with in vessel retention strategy applied to a generic PWR 900 MWe 208
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi 172
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants 158
ENEA activity in CESAM Project 151
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes 151
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes 146
DRACCAR code validation against the ballooned cluster experiment A2R038 of the ACHILLES experimental program 140
Synthesis of spent fuel pool accident assessments using severe accident codes 137
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 137
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling 133
ENEA Activities in the First 6 Months of 1998 131
DRACCAR code validation against unballooned cluster ACHILLES experiments 130
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 130
PHEBUS FPT3: Preliminary Investigation for Designing a Bundle with a B4C Rod 128
Analysis of BDBA sequences in a generic IRIS reactor using ASTEC code 124
Calculs complémentaires DRACCAR-2 en soutien à la préparation des essais TAGINE sur le réacteur BR2 124
ENEA Activities in the Last 6 Months of 1998 124
Investigation of Core Degradation (COBE). Final Report 123
ICARE V3 Mod0 Code Validation against MP-1 Experiment 120
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 119
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code 118
ICARE2 V3 Mod0 Validation against DC1 Experiment 117
Investigation of Core Degradation 115
Exploratory ICARE 2 Calculations for the PHEBUS FPT2 Test (Bundle Aspect) 114
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 113
Synthesis of the current understanding of the PHEBUS FP FPT2 test based on the ICARE2 code calculations 113
Post Test Analysis of PHEBUS FPTO Degradation Using the ICARE2 Debris Bed Model 111
PHEBUS FPT4: Epaisseur Dissoute et Reponse Thermique Associé du Boitier 110
Synthesis of IPSN Pre-Test Analysis for FPT0, the First Test of the PHEBUS FP Programme 108
Investigation of Core Degradation (COBE) 108
PHEBUS FPT4. First Post Test Calculation on the Debris Bed Using the ICARE2 V3 Code 106
PHEBUS FPT4: Progression Axial du Bain Fondu 104
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi 103
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison 103
Survey on FPT-3 Objectives and Pre-Test Analyses 102
PHEBUS FPT4: Pre-Test Calculation for the Debris Bed Using the ICARE2V3mod0 Code (as of September 1997), JC Crestia 101
New ICARE 2 Calculations and Sensitivity Studies for the FPT0 Test Piloting 101
PHEBUS FPT4: Sensitivity Calculation to the Debris Bed Relocation Temperature (2573 K) 100
PHEBUS FPT4: Minimum Cross Section of the Steam Chimney 100
PHEBUS FPT4: Expected Behaviour during the Melt Progression Phase. Gas Chimney Simulation with ICARE2 V3 Mod0 100
PHEBUS FPT4: Pressure Drop across the Debris Bed 97
Preliminary assessment of the DRACCAR thermo-hydraulic module. Comparison with CATHARE2 results on the simulation of a LOCA in a French PWR 97
Analysis of an unmitigated 2-inch cold leg LOCA transient with ASTEC and MELCOR codes 96
PHEBUS FPT4: Scenario Alternatif: Gonflement du Combustible 95
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test 95
PHEBUS FPT4: Aternative Scenarios: Steam Bypass through the Shroud 94
PHEBUS FPT2: Alternative Scenario: Sudden Debris Bed Formation. ICARE2 V3 Mod0 Calculation 93
PHEBUS FPT4: Alternative Scenario: Steam Bypass through the Shroud 93
PHEBUS FPT0 Post-test Analyses: Status of the Bundle Analysis Using ICARE/U2-MOD1 Code 90
Test of DRACCAR thermo-mechanical models on a Loss of coolant accident (LOCA) in Pressurized Water Reactors (PWrs), simulation. Comparison with CATHARE2 results 90
PHEBUS FPT3: Preliminary Model for the B4C Oxidation by Steam. Exploratory Calculations using ICARE2 Code. Proposals for the Test Scenario 87
Validation and uncertainty analysis of ASTEC in early degradation phase against QUENCH-06 experiment 84
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes 75
null 75
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 71
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 66
SBO analysis of a generic PWR-900 with ASTEC and MELCOR codes 55
Totale 7.045
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Categoria #
all - tutte 33.448
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 33.448
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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
2024/20254.340 11 142 33 49 226 165 115 180 322 161 1.277 1.659
Totale 7.045