statistiche ricercatore

Nome	Dominio	Durata	Descrizione
_pk.*	matomo.valueforyou.cineca.it	sessione	permette il tracciamento delle scelte fatte dall'utente

Nome	Dominio	Durata	Descrizione
s_.*	plu.mx	sessione	recupero grafico citazioni sociali da plumx
A_.*	core.ac.uk	7 giorni	recupero pubblicazioni consigliate per il pannello core-recommander
GS_.*	gstatic.com	richiesta http	visualizza grafico citazioni
CC_.*	creativecommons.org	richiesta http	visualizza licenza bitstream

MELONI, PARIDE

Distribuzione geografica

Continente	#
EU - Europa	6.182
NA - Nord America	3.895
AS - Asia	1.333
SA - Sud America	536
AF - Africa	35
Continente sconosciuto - Info sul continente non disponibili	24
OC - Oceania	9
Totale	12.014

Salva come PNG Salva come JPEG

Nazione	#
RU - Federazione Russa	4.023
US - Stati Uniti d'America	3.514
GB - Regno Unito	615
BR - Brasile	483
SG - Singapore	454
SE - Svezia	445
IT - Italia	400
CN - Cina	363
CA - Canada	360
DE - Germania	289
HK - Hong Kong	212
JP - Giappone	138
FR - Francia	113
FI - Finlandia	78
IN - India	49
AT - Austria	41
BE - Belgio	40
NL - Olanda	36
EU - Europa	23
UA - Ucraina	20
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	12.014

Salva come PNG Salva come JPEG

Città	#
Moscow	1.198
Chandler	1.143
San Mateo	342
Toronto	333
Southend	330
Santa Clara	325
Boardman	238
Hong Kong	211
Ashburn	198
Singapore	148
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
Munich	24
Los Angeles	21
Palermo	18
Rio de Janeiro	16
Shanghai	16
Frankfurt am Main	14
Trenton	14
Dong Ket	12
Amsterdam	11
Belo Horizonte	11
Brasília	11
Hefei	11
Turku	11
LaSalle	10
Nuremberg	10
Hamburg	9
Paris	9
San Jose	9
Tashkent	9
Tokyo	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	6.078

Salva come PNG Salva come JPEG

Nome	#
The SPES-3 Experimental Facility Design for the IRIS Reactor Integral Reactor Simulation	204
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	204
Application of fractional scaling analysis for development and design of integral effects test facility	163
SIET Experimental Facilities and Testing on LWR Passive Safety Systems	155
Natural Circulation of Lead-Bismuth in A-One-Dimensional Loop: Experiments and Code Predictions	151
Cold Leg Intermediate Break Experiment in SPES Facility and Post-Test Calculations with RELAP5 Mod 3.2 Code	143
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)	134
Design of the SPES-3 Experimental Facility for the IRIS Reactor Integral Reactor Simulation	134
LFR-120 Core neutronic verifications	131
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics	130
RELAP5 assessment on CIRCE decay heat removal experiments	128
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	124
He-Fus3 Facility Post Test Analysis of Steady State and Transient Experiments with ATHENA Code	123
Analysis of Thermal-Hydraulic Performance of IRIS/SPES3 EHRS Condenser with an Appropriate RELAP5 Model	122
Investigation of RELAP Capability to Simulate the LBE Cooling System Thermal-Hydraulic	121
HE-FUS3 benchmark results	121
Analytical Study with the ATHENA Code of the HCPB Blanket Design Experimental Activity on the He-FUS3 Facility	118
CATHARE 2 Analysis of the Small Break LOCA Experiment SP-SB-03, Conducted in SPES Facility	117
Benchmark Assessment of Cathare 2 V1.4 on a Loss of Residual Heat Removal System Test Conducted in Bethsy Facility	117
European Project for Future Advance s in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET)	117
Implementation and Preliminary Verification of the RELAP5/PARCS Code for Pb-Bi Cooled Subcritical Systems	117
Assessment of ATHENA Code Capability to Simulate Helium Cooled Systems for Fusion Reactors	116
Theoretical Design and Assessment of Isolation Condenser System Controlled with Thermal Valve Device	115
Overview of the CATHARE Use at ENEA for Innovative Safety Systems	115
Risk analysis of Nuclear Power Plants against External Events	115
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics	114
Design, experiments and Relap5 code calculations for the PERSEO facility	112
A Neutronics-Thermalhydraulics Model for Preliminary Studies on TRADE Dynamics	112
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio	112
INVESTIGATION OF RELAP CAPABILITY TO SIMULATE THE LBE COOLING SYSTEM THERMAL-HYDRAULIC	111
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster (BWRCA Project-Contract No. FI4I-CT96-0014)	111
The Italian Experience on T/H Best Estimate Codes: Achievements and Perspectives	110
HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis	110
Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop	110
Assessment of RELAP5 MOD3.3 and CATHARE2 V1.5A against a Full Scale Test of PERSEO Device	110
Benchmarking Activity on ENEA Available Tools for the Dynamic Analysis of LBE Cooled Subcritical Systems	109
Assessment of CATHARE Model of the PERSEO Device on Full-Scale Tests	109
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	109
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	109
Analytical Assessment of an Enhanced Configuration of Thermal Valve System	109
Accident Analysis of an Experimental Accelerator Driven System	108
BENCHMARKING ACTIVITY ON ENEA AVAILABLE TOOLS FOR THE DYNAMIC ANALYSIS OF LBE COOLED SUBCRITICAL SYSTEMS	106
The REPAS approach to the evaluation of passive safety systems reliability	106
Final Report on HE-FUS3 Benchmark Exercise	106
T/H and Transient Analyses to confirm EFIT Preliminary Design	105
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	105
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	105
He-FUS3 Facility Nodalization for ATHENA Code	104
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR	103
XADS source transients analyzed by means of RELAP5/PARCS	103
Description of the SI CATHARE module (models, utilisation)Deliverable D23 of DEEPSSI project	103
Analytical assessment of an enhanced configuration of Thermal Valve System	103
Comparison of Lead-Bismuth and Lead as Coolants for Accelerator Driven Systems	103
NATURAL CIRCULATION OF LEAD-BISMUTH IN A ONE-DIMENSIONAL LOOP: EXPERIMENTS AND CODE PREDICTIONS	102
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	102
Flowblockage accidents in the XADS plant analyzed by means of RELAP5/PARCS	101
In-Vessel Core Retention Strategy (IVCRS)	101
SPES3 Integral Tests: Organisation of Facility Analysis and Modelling	101
Application of RELAP5/Mod3 to the Testing of the AP600 Automatic Depressurization System	101
SPES 3-IRIS Facility Nodalization for RELAP5 Mod. 3.3 Code and Steady State Qualification	100
Loss of Coolant Accident in the ITER FW/SB Cooling Loop. A Comparison between ATHENA/INTRA and MELCOR Analyses	99
SPES3-IRIS Facility RELAP5 Base Case Transient Analyses for Design Support	99
Preliminary T/H and Transient Analyses for EFIT Reactor Design	99
Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop	98
Final SI CATHARE ModuleDeliverable D22 of DEEPSSI project	97
ENEA's activity in the Safety Analysis of the gas cooled eXperimental Accelerator Driven System (XADS)	96
Thermal-Hydraulic Analysis of the International Fusion Materials Irradiation Facility	95
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster(BWRCA project - Contract No. F141-CT96-0014)	94
RELAP5/MOD3 Capability to Simulate the Performance of Isolation Condenser Systems	94
Influence of the Break Location in the Loss of Coolant Accident Analyses for the Iter Divertor Cooling Loop	94
IVCRS - Half Yearly Progress Report	94
Application of the Capacity Module of the CATHARE Code to the Simulation of Reactor Containment during LOCA	94
INFLUENCE OF THE BREAK LOCATION IN THE LOSS OF COOLANT ACCIDENT ANALYSES FOR THE ITER DIVERTOR COOLING LOOP	93
PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations	92
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENTAL TESTS AND RELAP5 CODE	92
Sviluppo di un modello numerico per la simulazione del comportamento termoidraulico di un reattore raffreddato a piombo utilizzando il codice RELAP (Parte II)	92
Valutazione e modifica del codice termoidraulico di sistema cathare applicato a metalli liquidi pesanti e ai dati sperimentali del benchmark lacanes	92
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	91
ENEA's Activities on Nuclear Energy	90
Evaluation of CATHARE 2 V1.3 Capability to Simulate the Performance of Automatic Depressurization Systems in PWRs	89
Thermal Valve System for LWR Applications	88
MEGAPIE Post-Test Analysis for the RELAP5 Code Verification	88
SPES3-IRIS facility RELAP5 sensitivity analyses of the Lower Break transient for design support	88
Influence of the Break Location in the Loss of Coolant Accident Analyses for the ITER Divertor Cooling Loop	87
SPES-99 IBLOCA: RELAP5/Mod 3.2 Pre-Test and Post-Test Analysis	87
IFMIF Lithium LOCA Analyses with RELAP5 Code	87
THERMAL-HYDRAULIC ANALYSIS OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY	87
Overview of helium cooled system applications with RELAP at ENEA	87
RELAP5/Mod2 Analysis of the Station Blackout Experiment SP-ST-01, Performed in SPES Facility	86
BWR Physics and Thermalhydraulics Complementary Actions tot he IPSS-BWR R&D Clustei - Final Summary Report	86
GEST-SIP1 Experimental Campaign and Post-Test Calculations with the RELAP5 Code	85
Thermal-Hydraulics of Corium Pools	85
SPES-99 IBLOCA Analysis with the RELAP5 Mod 3.2 Code	84
In-Pool Energy Removal System for Emergency Operation: Experimental Tests and RELAP5 Code Calculations	84
Post-Test Calculations with ISAS-ITER Systems for ICE Experiments	84
Qualification of RELAP5-3D code condensation model against full-scale PERSEO Test 9	84
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENT AND ANALYTICAL ASSESSMENT	83
Protected and Unprotected Transients for the LBE Cooled eXperimental Accelerator Driven System ENEA's contribution to deliverable 45	83
Simulation of the PANDA Test for the ISP42 Using the CATHARE Code	82
Comparison of RELAP5/MOD3.2 and Cathare VI.3U Post Test Calculations of the BETHSY Test 6.9C	82
Totale	10.651

Salva come PNG Salva come JPEG

Categoria	#
all - tutte	69.303
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	69.303

Salva come PNG Salva come JPEG

	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2020/2021	900	15	18	2	13	240	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	6.642	20	323	81	98	419	85	348	390	352	230	2.275	2.021
Totale													12.040