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 #
NA - Nord America 3.723
EU - Europa 2.196
AS - Asia 1.145
SA - Sud America 437
AF - Africa 31
Continente sconosciuto - Info sul continente non disponibili 24
OC - Oceania 8
Totale 7.564
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Nazione #
US - Stati Uniti d'America 3.352
GB - Regno Unito 603
SE - Svezia 443
SG - Singapore 428
BR - Brasile 391
IT - Italia 389
CA - Canada 353
CN - Cina 349
DE - Germania 260
HK - Hong Kong 211
RU - Federazione Russa 140
FR - Francia 95
FI - Finlandia 67
BE - Belgio 40
IN - India 40
AT - Austria 37
NL - Olanda 32
EU - Europa 23
UA - Ucraina 19
JP - Giappone 17
AR - Argentina 15
ES - Italia 14
VN - Vietnam 12
KR - Corea 11
BD - Bangladesh 10
EC - Ecuador 10
IE - Irlanda 10
IR - Iran 10
RO - Romania 10
TR - Turchia 10
DZ - Algeria 8
CZ - Repubblica Ceca 7
UZ - Uzbekistan 7
ZA - Sudafrica 7
IQ - Iraq 6
AU - Australia 5
BO - Bolivia 5
CH - Svizzera 5
CO - Colombia 5
DO - Repubblica Dominicana 5
MA - Marocco 5
NP - Nepal 5
TW - Taiwan 5
PA - Panama 4
PE - Perù 4
PK - Pakistan 4
JM - Giamaica 3
JO - Giordania 3
KG - Kirghizistan 3
LT - Lituania 3
NZ - Nuova Zelanda 3
PT - Portogallo 3
SI - Slovenia 3
TN - Tunisia 3
AO - Angola 2
EE - Estonia 2
EG - Egitto 2
GT - Guatemala 2
HR - Croazia 2
HU - Ungheria 2
IL - Israele 2
KE - Kenya 2
KH - Cambogia 2
LV - Lettonia 2
MX - Messico 2
PL - Polonia 2
SA - Arabia Saudita 2
UY - Uruguay 2
VE - Venezuela 2
AM - Armenia 1
AZ - Azerbaigian 1
BN - Brunei Darussalam 1
BY - Bielorussia 1
CI - Costa d'Avorio 1
CL - Cile 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
NO - Norvegia 1
OM - Oman 1
PS - Palestinian Territory 1
PY - Paraguay 1
RS - Serbia 1
SK - Slovacchia (Repubblica Slovacca) 1
SN - Senegal 1
XK - ???statistics.table.value.countryCode.XK??? 1
Totale 7.564
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Città #
Chandler 1.143
San Mateo 342
Toronto 333
Southend 330
Santa Clara 323
Boardman 238
Hong Kong 210
Ashburn 193
Singapore 123
Berlin 120
New York 76
Helsinki 62
Falkenstein 61
Washington 61
Las Vegas 56
Council Bluffs 54
Rome 53
Beijing 52
Marseille 50
Ann Arbor 45
Bologna 40
Brussels 38
Miami 38
Milan 33
Redwood City 33
Guangzhou 28
Harbin 27
Mountain View 27
Vienna 26
São Paulo 22
Palermo 18
The Dalles 18
Los Angeles 17
Shanghai 16
Trenton 14
Dong Ket 12
Belo Horizonte 11
Hefei 11
Rio de Janeiro 11
Amsterdam 10
LaSalle 10
Brasília 9
Frankfurt am Main 9
Hamburg 9
Moscow 9
Nuremberg 9
Paris 9
Mazzano Romano 8
San Jose 8
Valencia 8
Falls Church 7
Tokyo 7
Dublin 6
Prague 6
St Petersburg 6
Stockholm 6
Tashkent 6
Bangalore 5
Campo Grande 5
Contagem 5
Curitiba 5
Goiânia 5
Limeira 5
Lyon 5
Manaus 5
Padova 5
Phoenix 5
Rockville 5
Salvador 5
Shenzhen 5
Zhengzhou 5
Baghdad 4
Belford Roxo 4
Borås 4
Buenos Aires 4
Campinas 4
Düsseldorf 4
Florence 4
Genoa 4
Karlsruhe 4
Kathmandu 4
London 4
Melbourne 4
North Bergen 4
Ovada 4
Pisa 4
Praia Grande 4
Recife 4
Redmond 4
Tsurumaki 4
Uberlândia 4
Viareggio 4
Vitória da Conquista 4
Amman 3
Cedar Knolls 3
Cerquilho 3
Changsha 3
Chicago 3
Dhaka 3
Esfahan 3
Totale 4.686
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Nome #
The SPES-3 Experimental Facility Design for the IRIS Reactor Integral Reactor Simulation 158
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 148
Application of fractional scaling analysis for development and design of integral effects test facility 123
SIET Experimental Facilities and Testing on LWR Passive Safety Systems 110
Cold Leg Intermediate Break Experiment in SPES Facility and Post-Test Calculations with RELAP5 Mod 3.2 Code 110
Natural Circulation of Lead-Bismuth in A-One-Dimensional Loop: Experiments and Code Predictions 93
Design of the SPES-3 Experimental Facility for the IRIS Reactor Integral Reactor Simulation 91
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics 91
LFR-120 Core neutronic verifications 91
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) 89
RELAP5 assessment on CIRCE decay heat removal experiments 83
European Project for Future Advance s in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET) 82
Design, experiments and Relap5 code calculations for the PERSEO facility 81
CATHARE 2 Analysis of the Small Break LOCA Experiment SP-SB-03, Conducted in SPES Facility 81
He-Fus3 Facility Post Test Analysis of Steady State and Transient Experiments with ATHENA Code 81
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997 81
HE-FUS3 benchmark results 80
Theoretical Design and Assessment of Isolation Condenser System Controlled with Thermal Valve Device 79
Investigation of RELAP Capability to Simulate the LBE Cooling System Thermal-Hydraulic 78
Analysis of Thermal-Hydraulic Performance of IRIS/SPES3 EHRS Condenser with an Appropriate RELAP5 Model 77
Implementation and Preliminary Verification of the RELAP5/PARCS Code for Pb-Bi Cooled Subcritical Systems 76
The REPAS approach to the evaluation of passive safety systems reliability 76
Risk analysis of Nuclear Power Plants against External Events 76
Benchmark Assessment of Cathare 2 V1.4 on a Loss of Residual Heat Removal System Test Conducted in Bethsy Facility 75
A Neutronics-Thermalhydraulics Model for Preliminary Studies on TRADE Dynamics 74
Overview of the CATHARE Use at ENEA for Innovative Safety Systems 74
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics 73
Analytical Study with the ATHENA Code of the HCPB Blanket Design Experimental Activity on the He-FUS3 Facility 72
Flowblockage accidents in the XADS plant analyzed by means of RELAP5/PARCS 71
Assessment of CATHARE Model of the PERSEO Device on Full-Scale Tests 71
SPES3 Integral Tests: Organisation of Facility Analysis and Modelling 71
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio 71
Analytical Assessment of an Enhanced Configuration of Thermal Valve System 70
SPES3-IRIS Facility RELAP5 Base Case Transient Analyses for Design Support 69
HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis 69
SPES 3-IRIS Facility Nodalization for RELAP5 Mod. 3.3 Code and Steady State Qualification 68
Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop 68
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code 67
Description of the SI CATHARE module (models, utilisation)Deliverable D23 of DEEPSSI project 67
INVESTIGATION OF RELAP CAPABILITY TO SIMULATE THE LBE COOLING SYSTEM THERMAL-HYDRAULIC 67
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations 67
Comparison of Lead-Bismuth and Lead as Coolants for Accelerator Driven Systems 67
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster (BWRCA Project-Contract No. FI4I-CT96-0014) 67
Benchmarking Activity on ENEA Available Tools for the Dynamic Analysis of LBE Cooled Subcritical Systems 66
The Italian Experience on T/H Best Estimate Codes: Achievements and Perspectives 66
Final SI CATHARE ModuleDeliverable D22 of DEEPSSI project 66
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments 66
Assessment of RELAP5 MOD3.3 and CATHARE2 V1.5A against a Full Scale Test of PERSEO Device 66
Assessment of ATHENA Code Capability to Simulate Helium Cooled Systems for Fusion Reactors 66
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments 65
BENCHMARKING ACTIVITY ON ENEA AVAILABLE TOOLS FOR THE DYNAMIC ANALYSIS OF LBE COOLED SUBCRITICAL SYSTEMS 65
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation 65
Analytical assessment of an enhanced configuration of Thermal Valve System 64
Accident Analysis of an Experimental Accelerator Driven System 63
In-Vessel Core Retention Strategy (IVCRS) 63
INFLUENCE OF THE BREAK LOCATION IN THE LOSS OF COOLANT ACCIDENT ANALYSES FOR THE ITER DIVERTOR COOLING LOOP 63
Final Report on HE-FUS3 Benchmark Exercise 63
Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop 63
T/H and Transient Analyses to confirm EFIT Preliminary Design 62
He-FUS3 Facility Nodalization for ATHENA Code 62
ENEA's activity in the Safety Analysis of the gas cooled eXperimental Accelerator Driven System (XADS) 61
Preliminary T/H and Transient Analyses for EFIT Reactor Design 61
ENEA's Activities on Nuclear Energy 60
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENTAL TESTS AND RELAP5 CODE 60
Thermal-Hydraulic Analysis of the International Fusion Materials Irradiation Facility 59
THERMAL-HYDRAULIC ANALYSIS OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY 59
Valutazione e modifica del codice termoidraulico di sistema cathare applicato a metalli liquidi pesanti e ai dati sperimentali del benchmark lacanes 59
Application of RELAP5/Mod3 to the Testing of the AP600 Automatic Depressurization System 59
Influence of the Break Location in the Loss of Coolant Accident Analyses for the ITER Divertor Cooling Loop 58
XADS source transients analyzed by means of RELAP5/PARCS 58
Influence of the Break Location in the Loss of Coolant Accident Analyses for the Iter Divertor Cooling Loop 58
Loss of Coolant Accident in the ITER FW/SB Cooling Loop. A Comparison between ATHENA/INTRA and MELCOR Analyses 58
SPES3-IRIS facility RELAP5 sensitivity analyses of the Lower Break transient for design support 58
RELAP5/MOD3 Capability to Simulate the Performance of Isolation Condenser Systems 57
MEGAPIE Post-Test Analysis for the RELAP5 Code Verification 57
NATURAL CIRCULATION OF LEAD-BISMUTH IN A ONE-DIMENSIONAL LOOP: EXPERIMENTS AND CODE PREDICTIONS 57
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster(BWRCA project - Contract No. F141-CT96-0014) 56
PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations 56
Sviluppo di un modello numerico per la simulazione del comportamento termoidraulico di un reattore raffreddato a piombo utilizzando il codice RELAP (Parte II) 56
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 55
Thermal Valve System for LWR Applications 55
IVCRS - Half Yearly Progress Report 55
Application of the Capacity Module of the CATHARE Code to the Simulation of Reactor Containment during LOCA 55
Simulation of the PANDA Test for the ISP42 Using the CATHARE Code 54
BWR Physics and Thermalhydraulics Complementary Actions tot he IPSS-BWR R&D Clustei - Final Summary Report 54
PERSEO project: experimental facility set-up and RELAP5 code calculations 54
Post-Test Calculations with ISAS-ITER Systems for ICE Experiments 54
GEST-SIP1 Experimental Campaign and Post-Test Calculations with the RELAP5 Code 53
SPES-99 IBLOCA: RELAP5/Mod 3.2 Pre-Test and Post-Test Analysis 52
In-Pool Energy Removal System for Emergency Operation: Experimental Tests and RELAP5 Code Calculations 52
Comparison of RELAP5/MOD3.2 and Cathare VI.3U Post Test Calculations of the BETHSY Test 6.9C 52
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENT AND ANALYTICAL ASSESSMENT 52
IFMIF Lithium LOCA Analyses with RELAP5 Code 52
SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code 51
Protected and Unprotected Transients for the LBE Cooled eXperimental Accelerator Driven System ENEA's contribution to deliverable 45 51
Design and Development of a Steam Generator Emergency Feedwater Passive System for Existing and Future PWRs Using Advanced Steam Injectors (DEEPSSI) 51
RELAP5/Mod2 Analysis of the Station Blackout Experiment SP-ST-01, Performed in SPES Facility 50
Overview of helium cooled system applications with RELAP at ENEA 50
Evaluation of CATHARE 2 V1.3 Capability to Simulate the Performance of Automatic Depressurization Systems in PWRs 50
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools 49
Totale 6.835
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Categoria #
all - tutte 53.306
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 53.306
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202028 0 0 0 0 0 0 0 0 0 24 4 0
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
2024/20252.186 20 323 81 98 419 85 348 390 352 70 0 0
Totale 7.584