statistiche ricercatore

MELONI, PARIDE

Distribuzione geografica

Continente	#
EU - Europa	7.624
NA - Nord America	6.144
AS - Asia	3.632
SA - Sud America	661
AF - Africa	141
Continente sconosciuto - Info sul continente non disponibili	24
OC - Oceania	10
Totale	18.236

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Nazione	#
US - Stati Uniti d'America	5.715
RU - Federazione Russa	5.253
SG - Singapore	1.769
CN - Cina	1.034
GB - Regno Unito	654
BR - Brasile	582
SE - Svezia	453
IT - Italia	430
CA - Canada	380
DE - Germania	332
HK - Hong Kong	256
JP - Giappone	150
FR - Francia	138
KR - Corea	133
FI - Finlandia	95
MA - Marocco	90
IN - India	74
VN - Vietnam	58
BE - Belgio	42
AT - Austria	41
ES - Italia	39
NL - Olanda	37
BD - Bangladesh	30
MX - Messico	27
AR - Argentina	25
EU - Europa	23
UA - Ucraina	21
TR - Turchia	19
IQ - Iraq	18
PL - Polonia	18
ZA - Sudafrica	18
EC - Ecuador	16
CO - Colombia	11
IE - Irlanda	11
IR - Iran	10
RO - Romania	10
UZ - Uzbekistan	10
CZ - Repubblica Ceca	9
CH - Svizzera	8
DZ - Algeria	8
ID - Indonesia	8
PK - Pakistan	8
VE - Venezuela	7
AU - Australia	6
LT - Lituania	6
SA - Arabia Saudita	6
BO - Bolivia	5
DO - Repubblica Dominicana	5
IL - Israele	5
JO - Giordania	5
KE - Kenya	5
NP - Nepal	5
TW - Taiwan	5
AE - Emirati Arabi Uniti	4
EG - Egitto	4
JM - Giamaica	4
PA - Panama	4
PE - Perù	4
TN - Tunisia	4
UY - Uruguay	4
AO - Angola	3
GR - Grecia	3
GT - Guatemala	3
KG - Kirghizistan	3
KZ - Kazakistan	3
NZ - Nuova Zelanda	3
PT - Portogallo	3
PY - Paraguay	3
SI - Slovenia	3
AM - Armenia	2
AZ - Azerbaigian	2
BG - Bulgaria	2
CI - Costa d'Avorio	2
CL - Cile	2
CY - Cipro	2
EE - Estonia	2
GY - Guiana	2
HR - Croazia	2
HU - Ungheria	2
KH - Cambogia	2
LV - Lettonia	2
MY - Malesia	2
NO - Norvegia	2
PH - Filippine	2
SN - Senegal	2
BA - Bosnia-Erzegovina	1
BH - Bahrain	1
BN - Brunei Darussalam	1
BY - Bielorussia	1
CG - Congo	1
CR - Costa Rica	1
ET - Etiopia	1
GD - Grenada	1
GE - Georgia	1
GH - Ghana	1
GN - Guinea	1
HN - Honduras	1
LB - Libano	1
LC - Santa Lucia	1
LK - Sri Lanka	1
Totale	18.225

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Città	#
Dallas	1.691
Moscow	1.283
Chandler	1.143
Singapore	875
Hefei	368
Santa Clara	350
San Mateo	342
Toronto	337
Ashburn	332
Southend	330
Hong Kong	255
Boardman	238
Beijing	188
Seoul	122
Berlin	120
New York	104
Casablanca	83
The Dalles	81
Helsinki	77
Council Bluffs	71
Columbus	70
Rome	65
Falkenstein	61
Washington	61
Las Vegas	57
Munich	57
Marseille	50
Los Angeles	48
São Paulo	46
Ann Arbor	45
Bologna	43
Brussels	40
Miami	39
Milan	35
Redwood City	33
Guangzhou	32
Harbin	28
Mountain View	27
Vienna	27
Paris	20
Shanghai	20
Rio de Janeiro	19
Palermo	18
Tokyo	17
Ho Chi Minh City	16
Phoenix	15
Stockholm	15
Warsaw	15
Atlanta	14
Brasília	14
Brooklyn	14
Frankfurt am Main	14
Trenton	14
Belo Horizonte	13
Chicago	13
Denver	13
Turku	13
Amsterdam	12
Chennai	12
Dong Ket	12
Montreal	12
Mexico City	11
Nuremberg	11
Boston	10
Curitiba	10
LaSalle	10
Poplar	10
Baghdad	9
Hamburg	9
Hanoi	9
Jülich	9
London	9
New Delhi	9
San Jose	9
Tashkent	9
Changsha	8
Dhaka	8
Houston	8
Johannesburg	8
Manchester	8
Mazzano Romano	8
Orem	8
Porto Alegre	8
St Petersburg	8
Turin	8
Valencia	8
Dublin	7
Falls Church	7
Recife	7
Genoa	6
Mumbai	6
Pisa	6
Prague	6
Ribeirão Preto	6
Salvador	6
Amman	5
Bangalore	5
Bexley	5
Buenos Aires	5
Campinas	5
Totale	9.883

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Nome	#
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	314
The SPES-3 Experimental Facility Design for the IRIS Reactor Integral Reactor Simulation	263
SIET Experimental Facilities and Testing on LWR Passive Safety Systems	246
Application of fractional scaling analysis for development and design of integral effects test facility	244
A Neutronics-Thermalhydraulics Model for Preliminary Studies on TRADE Dynamics	229
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics	223
Analysis of Thermal-Hydraulic Performance of IRIS/SPES3 EHRS Condenser with an Appropriate RELAP5 Model	222
Benchmarking Activity on ENEA Available Tools for the Dynamic Analysis of LBE Cooled Subcritical Systems	219
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	219
Analytical Study with the ATHENA Code of the HCPB Blanket Design Experimental Activity on the He-FUS3 Facility	217
Natural Circulation of Lead-Bismuth in A-One-Dimensional Loop: Experiments and Code Predictions	215
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics	213
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)	208
Benchmark Assessment of Cathare 2 V1.4 on a Loss of Residual Heat Removal System Test Conducted in Bethsy Facility	208
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	201
Assessment of CATHARE Model of the PERSEO Device on Full-Scale Tests	200
Accident Analysis of an Experimental Accelerator Driven System	198
Design of the SPES-3 Experimental Facility for the IRIS Reactor Integral Reactor Simulation	195
Assessment of ATHENA Code Capability to Simulate Helium Cooled Systems for Fusion Reactors	195
Assessment of RELAP5 MOD3.3 and CATHARE2 V1.5A against a Full Scale Test of PERSEO Device	193
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	192
LFR-120 Core neutronic verifications	192
Analytical Assessment of an Enhanced Configuration of Thermal Valve System	191
BENCHMARKING ACTIVITY ON ENEA AVAILABLE TOOLS FOR THE DYNAMIC ANALYSIS OF LBE COOLED SUBCRITICAL SYSTEMS	190
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster (BWRCA Project-Contract No. FI4I-CT96-0014)	189
Investigation of RELAP Capability to Simulate the LBE Cooling System Thermal-Hydraulic	188
Application of RELAP5/Mod3 to the Testing of the AP600 Automatic Depressurization System	188
Implementation and Preliminary Verification of the RELAP5/PARCS Code for Pb-Bi Cooled Subcritical Systems	186
He-Fus3 Facility Post Test Analysis of Steady State and Transient Experiments with ATHENA Code	185
RELAP5 assessment on CIRCE decay heat removal experiments	184
Cold Leg Intermediate Break Experiment in SPES Facility and Post-Test Calculations with RELAP5 Mod 3.2 Code	183
Analytical assessment of an enhanced configuration of Thermal Valve System	180
Application of the Capacity Module of the CATHARE Code to the Simulation of Reactor Containment during LOCA	179
Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop	173
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio	171
Qualification of RELAP5-3D Code Against the In-pool Passive Energy Removal System PERSEO Data	168
Final Report on HE-FUS3 Benchmark Exercise	168
Theoretical Design and Assessment of Isolation Condenser System Controlled with Thermal Valve Device	165
The Italian Experience on T/H Best Estimate Codes: Achievements and Perspectives	164
European Project for Future Advance s in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET)	163
INVESTIGATION OF RELAP CAPABILITY TO SIMULATE THE LBE COOLING SYSTEM THERMAL-HYDRAULIC	162
HE-FUS3 benchmark results	160
Overview of the CATHARE Use at ENEA for Innovative Safety Systems	158
Risk analysis of Nuclear Power Plants against External Events	156
CATHARE 2 Analysis of the Small Break LOCA Experiment SP-SB-03, Conducted in SPES Facility	155
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	155
T/H and Transient Analyses to confirm EFIT Preliminary Design	152
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	152
Design, experiments and Relap5 code calculations for the PERSEO facility	151
Flowblockage accidents in the XADS plant analyzed by means of RELAP5/PARCS	151
He-FUS3 Facility Nodalization for ATHENA Code	151
XADS source transients analyzed by means of RELAP5/PARCS	150
HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis	150
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	149
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	149
Comparison of Lead-Bismuth and Lead as Coolants for Accelerator Driven Systems	149
The REPAS approach to the evaluation of passive safety systems reliability	145
RELAP5/MOD3 Capability to Simulate the Performance of Isolation Condenser Systems	144
In-Vessel Core Retention Strategy (IVCRS)	143
Loss of Coolant Accident in the ITER FW/SB Cooling Loop. A Comparison between ATHENA/INTRA and MELCOR Analyses	141
Thermal-Hydraulic Analysis of the International Fusion Materials Irradiation Facility	140
Description of the SI CATHARE module (models, utilisation)Deliverable D23 of DEEPSSI project	140
SPES3-IRIS Facility RELAP5 Base Case Transient Analyses for Design Support	140
NATURAL CIRCULATION OF LEAD-BISMUTH IN A ONE-DIMENSIONAL LOOP: EXPERIMENTS AND CODE PREDICTIONS	139
PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations	138
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	137
Sviluppo di un modello numerico per la simulazione del comportamento termoidraulico di un reattore raffreddato a piombo utilizzando il codice RELAP (Parte II)	137
SPES3 Integral Tests: Organisation of Facility Analysis and Modelling	137
Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop	137
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster(BWRCA project - Contract No. F141-CT96-0014)	135
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENTAL TESTS AND RELAP5 CODE	135
Final SI CATHARE ModuleDeliverable D22 of DEEPSSI project	133
ENEA's activity in the Safety Analysis of the gas cooled eXperimental Accelerator Driven System (XADS)	133
SPES 3-IRIS Facility Nodalization for RELAP5 Mod. 3.3 Code and Steady State Qualification	133
Preliminary T/H and Transient Analyses for EFIT Reactor Design	133
Influence of the Break Location in the Loss of Coolant Accident Analyses for the Iter Divertor Cooling Loop	132
IVCRS - Half Yearly Progress Report	132
ENEA's Activities on Nuclear Energy	131
Valutazione e modifica del codice termoidraulico di sistema cathare applicato a metalli liquidi pesanti e ai dati sperimentali del benchmark lacanes	131
Overview of helium cooled system applications with RELAP at ENEA	131
Influence of the Break Location in the Loss of Coolant Accident Analyses for the ITER Divertor Cooling Loop	130
MEGAPIE Post-Test Analysis for the RELAP5 Code Verification	128
IFMIF Lithium LOCA Analyses with RELAP5 Code	128
State-of-the-art review of the T/H system codes RELAP5 for HLM applications	127
Thermal Valve System for LWR Applications	127
Simulation of the PANDA Test for the ISP42 Using the CATHARE Code	126
Final Report on the TV Modelization and Assessment	126
BWR Physics and Thermalhydraulics Complementary Actions tot he IPSS-BWR R&D Clustei - Final Summary Report	126
RELAP5/Mod2 Analysis of the Station Blackout Experiment SP-ST-01, Performed in SPES Facility	124
Thermal-Hydraulics of Corium Pools	124
GEST-SIP1 Experimental Campaign and Post-Test Calculations with the RELAP5 Code	123
SPES-99 IBLOCA: RELAP5/Mod 3.2 Pre-Test and Post-Test Analysis	122
SPES3-IRIS facility RELAP5 sensitivity analyses of the Lower Break transient for design support	122
Evaluation of CATHARE 2 V1.3 Capability to Simulate the Performance of Automatic Depressurization Systems in PWRs	122
Protected and Unprotected Transients for the LBE Cooled eXperimental Accelerator Driven System ENEA's contribution to deliverable 45	121
INFLUENCE OF THE BREAK LOCATION IN THE LOSS OF COOLANT ACCIDENT ANALYSES FOR THE ITER DIVERTOR COOLING LOOP	121
Post-Test Calculations with ISAS-ITER Systems for ICE Experiments	121
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	121
THERMAL-HYDRAULIC ANALYSIS OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY	119
SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code	118
Totale	16.224

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Categoria	#
all - tutte	83.307
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	83.307

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	612	0	0	0	0	0	14	10	95	86	37	341	29
2021/2022	1.188	9	347	47	72	138	19	34	293	50	13	60	106
2022/2023	2.109	149	410	144	285	94	365	18	186	285	93	31	49
2023/2024	1.136	67	57	174	26	140	167	44	133	48	71	64	145
2024/2025	7.815	20	323	81	98	419	85	348	390	352	230	2.275	3.194
2025/2026	5.049	830	1.692	1.221	718	407	181	0	0	0	0	0	0
Totale													18.262