MELONI, PARIDE
 Distribuzione geografica
Continente #
NA - Nord America 3.076
EU - Europa 1.950
AS - Asia 322
Continente sconosciuto - Info sul continente non disponibili 23
OC - Oceania 8
AF - Africa 5
SA - Sud America 4
Totale 5.388
Nazione #
US - Stati Uniti d'America 2.738
GB - Regno Unito 599
SE - Svezia 442
CA - Canada 338
IT - Italia 337
CN - Cina 179
DE - Germania 169
RU - Federazione Russa 122
FR - Francia 82
FI - Finlandia 62
SG - Singapore 41
IN - India 39
BE - Belgio 36
AT - Austria 31
EU - Europa 23
HK - Hong Kong 17
ES - Italia 13
NL - Olanda 13
VN - Vietnam 12
JP - Giappone 11
UA - Ucraina 10
IE - Irlanda 9
IR - Iran 9
RO - Romania 8
CZ - Repubblica Ceca 7
KR - Corea 7
AU - Australia 5
CH - Svizzera 5
DZ - Algeria 5
BR - Brasile 4
NZ - Nuova Zelanda 3
TW - Taiwan 3
SA - Arabia Saudita 2
SI - Slovenia 2
TR - Turchia 2
HU - Ungheria 1
LU - Lussemburgo 1
PL - Polonia 1
Totale 5.388
Città #
Chandler 1.143
San Mateo 342
Southend 330
Toronto 328
Ashburn 172
Boardman 121
Berlin 120
New York 62
Washington 61
Helsinki 57
Las Vegas 56
Marseille 50
Beijing 48
Ann Arbor 45
Rome 44
Bologna 38
Brussels 34
Redwood City 33
Harbin 27
Mountain View 27
Vienna 23
Guangzhou 21
Singapore 20
Palermo 17
Hong Kong 16
Milan 16
Miami 15
Los Angeles 14
Trenton 14
Shanghai 13
Dong Ket 12
Hefei 11
Paris 9
Mazzano Romano 8
Valencia 8
Falls Church 7
Prague 6
Bangalore 5
Dublin 5
Padova 5
Rockville 5
St Petersburg 5
Stockholm 5
Zhengzhou 5
Borås 4
Florence 4
Karlsruhe 4
Melbourne 4
Ovada 4
Phoenix 4
Redmond 4
Tsurumaki 4
Viareggio 4
Cedar Knolls 3
Chicago 3
Esfahan 3
Frankfurt am Main 3
Lyon 3
Mioveni 3
Moscow 3
Naples 3
Napoli 3
Orenburg 3
Pisa 3
San Jose 3
São Paulo 3
Taipei 3
Tokyo 3
Villigen 3
Wilmington 3
Amsterdam 2
Bresso 2
Brighton 2
Broomfield 2
Canale Monterano 2
Chalk River 2
Chengdu 2
Como 2
Duncan 2
Gatchina 2
Ig 2
Jinan 2
Kundan 2
Lafayette 2
Lappeenranta 2
Legnaro 2
Livorno 2
London 2
Madrid 2
Mumbai 2
Munich 2
North Bergen 2
Podolsk 2
Prayagraj 2
Riyadh 2
Roquemaure 2
Seoul 2
Sheffield 2
Siena 2
Tortona 2
Totale 3.550
Nome #
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione 121
Application of fractional scaling analysis for development and design of integral effects test facility 99
The SPES-3 Experimental Facility Design for the IRIS Reactor Integral Reactor Simulation 88
Natural Circulation of Lead-Bismuth in A-One-Dimensional Loop: Experiments and Code Predictions 71
CATHARE 2 Analysis of the Small Break LOCA Experiment SP-SB-03, Conducted in SPES Facility 68
Cold Leg Intermediate Break Experiment in SPES Facility and Post-Test Calculations with RELAP5 Mod 3.2 Code 67
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) 66
LFR-120 Core neutronic verifications 66
European Project for Future Advance s in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET) 65
Theoretical Design and Assessment of Isolation Condenser System Controlled with Thermal Valve Device 63
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997 63
Design, experiments and Relap5 code calculations for the PERSEO facility 62
The REPAS approach to the evaluation of passive safety systems reliability 62
He-Fus3 Facility Post Test Analysis of Steady State and Transient Experiments with ATHENA Code 61
HE-FUS3 benchmark results 61
Investigation of RELAP Capability to Simulate the LBE Cooling System Thermal-Hydraulic 59
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio 59
Risk analysis of Nuclear Power Plants against External Events 58
Overview of the CATHARE Use at ENEA for Innovative Safety Systems 57
Design of the SPES-3 Experimental Facility for the IRIS Reactor Integral Reactor Simulation 56
SPES 3-IRIS Facility Nodalization for RELAP5 Mod. 3.3 Code and Steady State Qualification 56
SPES3 Integral Tests: Organisation of Facility Analysis and Modelling 56
Comparison of Lead-Bismuth and Lead as Coolants for Accelerator Driven Systems 56
Analytical Study with the ATHENA Code of the HCPB Blanket Design Experimental Activity on the He-FUS3 Facility 55
Implementation and Preliminary Verification of the RELAP5/PARCS Code for Pb-Bi Cooled Subcritical Systems 55
Analysis of Thermal-Hydraulic Performance of IRIS/SPES3 EHRS Condenser with an Appropriate RELAP5 Model 55
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code 54
Assessment of CATHARE Model of the PERSEO Device on Full-Scale Tests 52
SIET Experimental Facilities and Testing on LWR Passive Safety Systems 52
Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop 52
Benchmarking Activity on ENEA Available Tools for the Dynamic Analysis of LBE Cooled Subcritical Systems 51
SPES3-IRIS Facility RELAP5 Base Case Transient Analyses for Design Support 51
HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis 51
Assessment of RELAP5 MOD3.3 and CATHARE2 V1.5A against a Full Scale Test of PERSEO Device 51
Analytical Assessment of an Enhanced Configuration of Thermal Valve System 51
A Neutronics-Thermalhydraulics Model for Preliminary Studies on TRADE Dynamics 50
Benchmark Assessment of Cathare 2 V1.4 on a Loss of Residual Heat Removal System Test Conducted in Bethsy Facility 50
Final SI CATHARE ModuleDeliverable D22 of DEEPSSI project 49
Influence of the Break Location in the Loss of Coolant Accident Analyses for the ITER Divertor Cooling Loop 48
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics 48
In-Vessel Core Retention Strategy (IVCRS) 48
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics 48
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations 48
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments 47
Influence of the Break Location in the Loss of Coolant Accident Analyses for the Iter Divertor Cooling Loop 47
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENTAL TESTS AND RELAP5 CODE 47
ENEA's activity in the Safety Analysis of the gas cooled eXperimental Accelerator Driven System (XADS) 47
Final Report on HE-FUS3 Benchmark Exercise 47
Assessment of ATHENA Code Capability to Simulate Helium Cooled Systems for Fusion Reactors 47
Flowblockage accidents in the XADS plant analyzed by means of RELAP5/PARCS 46
T/H and Transient Analyses to confirm EFIT Preliminary Design 46
Accident Analysis of an Experimental Accelerator Driven System 46
ENEA's Activities on Nuclear Energy 46
Loss of Coolant Accident in the ITER FW/SB Cooling Loop. A Comparison between ATHENA/INTRA and MELCOR Analyses 46
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments 46
BENCHMARKING ACTIVITY ON ENEA AVAILABLE TOOLS FOR THE DYNAMIC ANALYSIS OF LBE COOLED SUBCRITICAL SYSTEMS 46
Analytical assessment of an enhanced configuration of Thermal Valve System 46
The Italian Experience on T/H Best Estimate Codes: Achievements and Perspectives 45
Description of the SI CATHARE module (models, utilisation)Deliverable D23 of DEEPSSI project 45
THERMAL-HYDRAULIC ANALYSIS OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY 45
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster (BWRCA Project-Contract No. FI4I-CT96-0014) 45
INVESTIGATION OF RELAP CAPABILITY TO SIMULATE THE LBE COOLING SYSTEM THERMAL-HYDRAULIC 44
Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop 44
Simulation of the PANDA Test for the ISP42 Using the CATHARE Code 43
In-Pool Energy Removal System for Emergency Operation: Experimental Tests and RELAP5 Code Calculations 43
He-FUS3 Facility Nodalization for ATHENA Code 43
Sviluppo di un modello numerico per la simulazione del comportamento termoidraulico di un reattore raffreddato a piombo utilizzando il codice RELAP (Parte II) 43
INFLUENCE OF THE BREAK LOCATION IN THE LOSS OF COOLANT ACCIDENT ANALYSES FOR THE ITER DIVERTOR COOLING LOOP 43
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation 43
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster(BWRCA project - Contract No. F141-CT96-0014) 42
Thermal Valve System for LWR Applications 42
Preliminary T/H and Transient Analyses for EFIT Reactor Design 42
XADS source transients analyzed by means of RELAP5/PARCS 41
Thermal-Hydraulic Analysis of the International Fusion Materials Irradiation Facility 41
SPES-99 IBLOCA: RELAP5/Mod 3.2 Pre-Test and Post-Test Analysis 40
PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations 40
MEGAPIE Post-Test Analysis for the RELAP5 Code Verification 40
Valutazione e modifica del codice termoidraulico di sistema cathare applicato a metalli liquidi pesanti e ai dati sperimentali del benchmark lacanes 40
Post-Test Calculations with ISAS-ITER Systems for ICE Experiments 40
Application of RELAP5/Mod3 to the Testing of the AP600 Automatic Depressurization System 40
RELAP5 assessment on CIRCE decay heat removal experiments 39
NATURAL CIRCULATION OF LEAD-BISMUTH IN A ONE-DIMENSIONAL LOOP: EXPERIMENTS AND CODE PREDICTIONS 39
SPES3-IRIS facility RELAP5 sensitivity analyses of the Lower Break transient for design support 39
Evaluation of CATHARE 2 V1.3 Capability to Simulate the Performance of Automatic Depressurization Systems in PWRs 39
Comparison of RELAP5/MOD3.2 and Cathare VI.3U Post Test Calculations of the BETHSY Test 6.9C 38
BWR Physics and Thermalhydraulics Complementary Actions tot he IPSS-BWR R&D Clustei - Final Summary Report 38
PERSEO project: experimental facility set-up and RELAP5 code calculations 38
Overview of helium cooled system applications with RELAP at ENEA 38
RELAP5/MOD3 Capability to Simulate the Performance of Isolation Condenser Systems 37
IVCRS - Half Yearly Progress Report 37
IFMIF Lithium LOCA Analyses with RELAP5 Code 37
Application of the Capacity Module of the CATHARE Code to the Simulation of Reactor Containment during LOCA 37
Design and Development of a Steam Generator Emergency Feedwater Passive System for Existing and Future PWRs Using Advanced Steam Injectors (DEEPSSI) 37
Protected and Unprotected Transients for the LBE Cooled eXperimental Accelerator Driven System ENEA's contribution to deliverable 45 35
CATHARE 2 V 1.4 Capability to Simulate the Performance of ISOLATION CONDENSER SYSTEMS with Thermal Valve 34
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools 34
Thermal-Hydraulics of Corium Pools 34
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENT AND ANALYTICAL ASSESSMENT 34
SPES 6 Small Break LOCA Post-test Analysis Using CATHARE 2 Code 33
SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code 33
Totale 4.913
Categoria #
all - tutte 40.066
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 40.066


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/202065 0 0 0 3 7 5 14 5 3 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
2024/20254 4 0 0 0 0 0 0 0 0 0 0 0
Totale 5.402