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.

MELONI, PARIDE
 Distribuzione geografica
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Continente #
EU - Europa 5.477
NA - Nord America 3.893
AS - Asia 1.206
SA - Sud America 536
AF - Africa 35
Continente sconosciuto - Info sul continente non disponibili 24
OC - Oceania 9
Totale 11.180
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Nazione #
US - Stati Uniti d'America 3.512
RU - Federazione Russa 3.338
GB - Regno Unito 614
BR - Brasile 483
SG - Singapore 446
SE - Svezia 445
IT - Italia 400
CN - Cina 363
CA - Canada 360
DE - Germania 276
HK - Hong Kong 212
FR - Francia 111
FI - Finlandia 76
IN - India 49
AT - Austria 40
BE - Belgio 40
NL - Olanda 35
EU - Europa 23
UA - Ucraina 20
JP - Giappone 19
AR - Argentina 17
ES - Italia 16
BD - Bangladesh 15
TR - Turchia 15
VN - Vietnam 12
IE - Irlanda 11
KR - Corea 11
EC - Ecuador 10
IR - Iran 10
RO - Romania 10
UZ - Uzbekistan 10
CZ - Repubblica Ceca 9
DZ - Algeria 8
IQ - Iraq 8
CO - Colombia 7
ZA - Sudafrica 7
AU - Australia 6
MA - Marocco 6
PL - Polonia 6
BO - Bolivia 5
CH - Svizzera 5
DO - Repubblica Dominicana 5
MX - Messico 5
NP - Nepal 5
TW - Taiwan 5
EG - Egitto 4
JO - Giordania 4
PA - Panama 4
PE - Perù 4
PK - Pakistan 4
TN - Tunisia 4
IL - Israele 3
JM - Giamaica 3
KG - Kirghizistan 3
LT - Lituania 3
NZ - Nuova Zelanda 3
PT - Portogallo 3
SI - Slovenia 3
VE - Venezuela 3
AO - Angola 2
CL - Cile 2
EE - Estonia 2
GT - Guatemala 2
HR - Croazia 2
HU - Ungheria 2
KE - Kenya 2
KH - Cambogia 2
LV - Lettonia 2
PY - Paraguay 2
SA - Arabia Saudita 2
UY - Uruguay 2
AM - Armenia 1
AZ - Azerbaigian 1
BA - Bosnia-Erzegovina 1
BN - Brunei Darussalam 1
BY - Bielorussia 1
CI - Costa d'Avorio 1
GR - Grecia 1
GY - Guiana 1
HN - Honduras 1
ID - Indonesia 1
KZ - Kazakistan 1
LC - Santa Lucia 1
LK - Sri Lanka 1
LU - Lussemburgo 1
MD - Moldavia 1
NO - Norvegia 1
OM - Oman 1
PS - Palestinian Territory 1
RS - Serbia 1
SK - Slovacchia (Repubblica Slovacca) 1
SN - Senegal 1
XK - ???statistics.table.value.countryCode.XK??? 1
Totale 11.180
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Città #
Chandler 1.143
Moscow 1.089
San Mateo 342
Toronto 333
Southend 330
Santa Clara 325
Boardman 238
Hong Kong 211
Ashburn 197
Singapore 141
Berlin 120
New York 80
The Dalles 79
Helsinki 62
Falkenstein 61
Washington 61
Beijing 59
Rome 58
Las Vegas 56
Council Bluffs 54
Marseille 50
Ann Arbor 45
Bologna 40
Brussels 38
Miami 38
Milan 33
Redwood City 33
São Paulo 32
Guangzhou 28
Harbin 27
Mountain View 27
Vienna 27
Los Angeles 21
Palermo 18
Rio de Janeiro 16
Shanghai 16
Frankfurt am Main 14
Trenton 14
Dong Ket 12
Munich 12
Amsterdam 11
Belo Horizonte 11
Brasília 11
Hefei 11
LaSalle 10
Hamburg 9
Nuremberg 9
Paris 9
San Jose 9
Tashkent 9
Tokyo 9
Turku 9
Mazzano Romano 8
St Petersburg 8
Stockholm 8
Valencia 8
Curitiba 7
Dublin 7
Falls Church 7
Phoenix 7
Baghdad 6
Pisa 6
Prague 6
Recife 6
Salvador 6
Bangalore 5
Bexley 5
Brooklyn 5
Campinas 5
Campo Grande 5
Chennai 5
Contagem 5
Dhaka 5
Goiânia 5
Limeira 5
London 5
Lyon 5
Manaus 5
Padova 5
Porto Alegre 5
Ribeirão Preto 5
Rockville 5
Shenzhen 5
Zhengzhou 5
Amman 4
Atlanta 4
Belford Roxo 4
Borås 4
Buenos Aires 4
Chicago 4
Düsseldorf 4
Florence 4
Genoa 4
Istanbul 4
Karlsruhe 4
Kathmandu 4
Melbourne 4
Montes Claros 4
North Bergen 4
Ovada 4
Totale 5.946
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Nome #
The SPES-3 Experimental Facility Design for the IRIS Reactor Integral Reactor Simulation 195
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 194
Application of fractional scaling analysis for development and design of integral effects test facility 158
SIET Experimental Facilities and Testing on LWR Passive Safety Systems 145
Natural Circulation of Lead-Bismuth in A-One-Dimensional Loop: Experiments and Code Predictions 140
Cold Leg Intermediate Break Experiment in SPES Facility and Post-Test Calculations with RELAP5 Mod 3.2 Code 137
Design of the SPES-3 Experimental Facility for the IRIS Reactor Integral Reactor Simulation 126
Cross-comparison of one-dimensional thermal-hydraulic codes on natural circulation analysis of NACIE loop test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES) 125
LFR-120 Core neutronic verifications 124
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics 123
RELAP5 assessment on CIRCE decay heat removal experiments 119
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997 116
He-Fus3 Facility Post Test Analysis of Steady State and Transient Experiments with ATHENA Code 114
Analytical Study with the ATHENA Code of the HCPB Blanket Design Experimental Activity on the He-FUS3 Facility 113
Analysis of Thermal-Hydraulic Performance of IRIS/SPES3 EHRS Condenser with an Appropriate RELAP5 Model 113
HE-FUS3 benchmark results 113
Investigation of RELAP Capability to Simulate the LBE Cooling System Thermal-Hydraulic 112
European Project for Future Advance s in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET) 112
CATHARE 2 Analysis of the Small Break LOCA Experiment SP-SB-03, Conducted in SPES Facility 111
Implementation and Preliminary Verification of the RELAP5/PARCS Code for Pb-Bi Cooled Subcritical Systems 111
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics 109
Theoretical Design and Assessment of Isolation Condenser System Controlled with Thermal Valve Device 109
Benchmark Assessment of Cathare 2 V1.4 on a Loss of Residual Heat Removal System Test Conducted in Bethsy Facility 109
Overview of the CATHARE Use at ENEA for Innovative Safety Systems 109
Design, experiments and Relap5 code calculations for the PERSEO facility 106
A Neutronics-Thermalhydraulics Model for Preliminary Studies on TRADE Dynamics 106
Risk analysis of Nuclear Power Plants against External Events 105
Assessment of ATHENA Code Capability to Simulate Helium Cooled Systems for Fusion Reactors 105
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio 104
Assessment of CATHARE Model of the PERSEO Device on Full-Scale Tests 103
The Italian Experience on T/H Best Estimate Codes: Achievements and Perspectives 103
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations 102
HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis 102
Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop 102
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code 101
The REPAS approach to the evaluation of passive safety systems reliability 101
Assessment of RELAP5 MOD3.3 and CATHARE2 V1.5A against a Full Scale Test of PERSEO Device 101
Analytical Assessment of an Enhanced Configuration of Thermal Valve System 101
Accident Analysis of an Experimental Accelerator Driven System 100
INVESTIGATION OF RELAP CAPABILITY TO SIMULATE THE LBE COOLING SYSTEM THERMAL-HYDRAULIC 100
Benchmarking Activity on ENEA Available Tools for the Dynamic Analysis of LBE Cooled Subcritical Systems 99
Final Report on HE-FUS3 Benchmark Exercise 99
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster (BWRCA Project-Contract No. FI4I-CT96-0014) 99
He-FUS3 Facility Nodalization for ATHENA Code 98
BENCHMARKING ACTIVITY ON ENEA AVAILABLE TOOLS FOR THE DYNAMIC ANALYSIS OF LBE COOLED SUBCRITICAL SYSTEMS 98
Comparison of Lead-Bismuth and Lead as Coolants for Accelerator Driven Systems 98
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments 97
T/H and Transient Analyses to confirm EFIT Preliminary Design 96
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments 96
Analytical assessment of an enhanced configuration of Thermal Valve System 96
SPES3 Integral Tests: Organisation of Facility Analysis and Modelling 96
In-Vessel Core Retention Strategy (IVCRS) 95
Description of the SI CATHARE module (models, utilisation)Deliverable D23 of DEEPSSI project 95
NATURAL CIRCULATION OF LEAD-BISMUTH IN A ONE-DIMENSIONAL LOOP: EXPERIMENTS AND CODE PREDICTIONS 95
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation 95
SPES3-IRIS Facility RELAP5 Base Case Transient Analyses for Design Support 95
Flowblockage accidents in the XADS plant analyzed by means of RELAP5/PARCS 94
XADS source transients analyzed by means of RELAP5/PARCS 94
SPES 3-IRIS Facility Nodalization for RELAP5 Mod. 3.3 Code and Steady State Qualification 94
Application of RELAP5/Mod3 to the Testing of the AP600 Automatic Depressurization System 94
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 93
Preliminary T/H and Transient Analyses for EFIT Reactor Design 93
Final SI CATHARE ModuleDeliverable D22 of DEEPSSI project 92
Loss of Coolant Accident in the ITER FW/SB Cooling Loop. A Comparison between ATHENA/INTRA and MELCOR Analyses 91
ENEA's activity in the Safety Analysis of the gas cooled eXperimental Accelerator Driven System (XADS) 90
Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop 90
Influence of the Break Location in the Loss of Coolant Accident Analyses for the Iter Divertor Cooling Loop 89
Thermal-Hydraulic Analysis of the International Fusion Materials Irradiation Facility 88
RELAP5/MOD3 Capability to Simulate the Performance of Isolation Condenser Systems 87
IVCRS - Half Yearly Progress Report 87
Application of the Capacity Module of the CATHARE Code to the Simulation of Reactor Containment during LOCA 87
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster(BWRCA project - Contract No. F141-CT96-0014) 86
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENTAL TESTS AND RELAP5 CODE 86
INFLUENCE OF THE BREAK LOCATION IN THE LOSS OF COOLANT ACCIDENT ANALYSES FOR THE ITER DIVERTOR COOLING LOOP 86
Sviluppo di un modello numerico per la simulazione del comportamento termoidraulico di un reattore raffreddato a piombo utilizzando il codice RELAP (Parte II) 85
Valutazione e modifica del codice termoidraulico di sistema cathare applicato a metalli liquidi pesanti e ai dati sperimentali del benchmark lacanes 85
ENEA's Activities on Nuclear Energy 83
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools 83
THERMAL-HYDRAULIC ANALYSIS OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY 83
SPES3-IRIS facility RELAP5 sensitivity analyses of the Lower Break transient for design support 83
SPES-99 IBLOCA: RELAP5/Mod 3.2 Pre-Test and Post-Test Analysis 82
PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations 82
MEGAPIE Post-Test Analysis for the RELAP5 Code Verification 82
Evaluation of CATHARE 2 V1.3 Capability to Simulate the Performance of Automatic Depressurization Systems in PWRs 82
Influence of the Break Location in the Loss of Coolant Accident Analyses for the ITER Divertor Cooling Loop 81
Thermal Valve System for LWR Applications 81
GEST-SIP1 Experimental Campaign and Post-Test Calculations with the RELAP5 Code 80
RELAP5/Mod2 Analysis of the Station Blackout Experiment SP-ST-01, Performed in SPES Facility 80
Post-Test Calculations with ISAS-ITER Systems for ICE Experiments 80
Overview of helium cooled system applications with RELAP at ENEA 80
SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code 79
In-Pool Energy Removal System for Emergency Operation: Experimental Tests and RELAP5 Code Calculations 79
Thermal-Hydraulics of Corium Pools 78
BWR Physics and Thermalhydraulics Complementary Actions tot he IPSS-BWR R&D Clustei - Final Summary Report 78
IFMIF Lithium LOCA Analyses with RELAP5 Code 78
Simulation of the PANDA Test for the ISP42 Using the CATHARE Code 77
Comparison of RELAP5/MOD3.2 and Cathare VI.3U Post Test Calculations of the BETHSY Test 6.9C 77
PERSEO project: experimental facility set-up and RELAP5 code calculations 77
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENT AND ANALYTICAL ASSESSMENT 76
Protected and Unprotected Transients for the LBE Cooled eXperimental Accelerator Driven System ENEA's contribution to deliverable 45 76
Totale 9.934
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Categoria #
all - tutte 61.302
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 61.302
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021900 15 18 2 13 240 14 10 95 86 37 341 29
2021/20221.188 9 347 47 72 138 19 34 293 50 13 60 106
2022/20232.109 149 410 144 285 94 365 18 186 285 93 31 49
2023/20241.136 67 57 174 26 140 167 44 133 48 71 64 145
2024/20255.808 20 323 81 98 419 85 348 390 352 230 2.275 1.187
Totale 11.206