statistiche ricercatore

MELONI, PARIDE

Distribuzione geografica

Continente	#
NA - Nord America	3.358
EU - Europa	1.987
AS - Asia	649
Continente sconosciuto - Info sul continente non disponibili	23
SA - Sud America	16
AF - Africa	9
OC - Oceania	8
Totale	6.050

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Nazione	#
US - Stati Uniti d'America	3.017
GB - Regno Unito	599
SE - Svezia	443
IT - Italia	353
CA - Canada	338
CN - Cina	334
SG - Singapore	195
DE - Germania	170
RU - Federazione Russa	123
FR - Francia	88
FI - Finlandia	65
IN - India	39
BE - Belgio	36
AT - Austria	31
EU - Europa	23
HK - Hong Kong	17
JP - Giappone	16
BR - Brasile	15
NL - Olanda	15
ES - Italia	13
VN - Vietnam	12
UA - Ucraina	11
IR - Iran	10
KR - Corea	10
IE - Irlanda	9
RO - Romania	8
CZ - Repubblica Ceca	7
AU - Australia	5
CH - Svizzera	5
DZ - Algeria	5
TW - Taiwan	5
NZ - Nuova Zelanda	3
BD - Bangladesh	2
DO - Repubblica Dominicana	2
EG - Egitto	2
HR - Croazia	2
PL - Polonia	2
SA - Arabia Saudita	2
SI - Slovenia	2
TR - Turchia	2
ZA - Sudafrica	2
AM - Armenia	1
EE - Estonia	1
HU - Ungheria	1
ID - Indonesia	1
IQ - Iraq	1
KG - Kirghizistan	1
LU - Lussemburgo	1
LV - Lettonia	1
NP - Nepal	1
PA - Panama	1
PE - Perù	1
SK - Slovacchia (Repubblica Slovacca)	1
Totale	6.050

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Città	#
Chandler	1.143
San Mateo	342
Southend	330
Toronto	328
Boardman	238
Ashburn	189
Berlin	120
Santa Clara	102
Singapore	85
New York	76
Washington	61
Helsinki	60
Las Vegas	56
Beijing	51
Marseille	50
Ann Arbor	45
Rome	45
Bologna	40
Miami	38
Brussels	34
Redwood City	33
Guangzhou	27
Harbin	27
Mountain View	27
Vienna	23
Milan	21
Palermo	17
Hong Kong	16
Shanghai	15
Los Angeles	14
Trenton	14
Dong Ket	12
Hefei	11
Paris	9
Mazzano Romano	8
Valencia	8
Falls Church	7
Tokyo	7
Prague	6
Stockholm	6
Bangalore	5
Dublin	5
Lyon	5
Padova	5
Phoenix	5
Rockville	5
St Petersburg	5
Zhengzhou	5
Borås	4
Florence	4
Karlsruhe	4
Melbourne	4
Ovada	4
Pisa	4
Redmond	4
Shenzhen	4
Tsurumaki	4
Viareggio	4
Amsterdam	3
Cedar Knolls	3
Chicago	3
Esfahan	3
Frankfurt am Main	3
Mioveni	3
Moscow	3
Naples	3
Napoli	3
Orenburg	3
San Jose	3
Seo-gu	3
São Paulo	3
Taipei	3
Turin	3
Villigen	3
Wilmington	3
Bresso	2
Brighton	2
Broomfield	2
Canale Monterano	2
Chalk River	2
Changsha	2
Chengdu	2
Como	2
Duncan	2
Eugene	2
Gatchina	2
Genoa	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
Pedernales	2
Totale	3.922

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Nome	#
Raccolta delle relazioni di partecipazione ai comitati e gruppi internazionali sul nucIeare da fissione	126
The SPES-3 Experimental Facility Design for the IRIS Reactor Integral Reactor Simulation	118
Application of fractional scaling analysis for development and design of integral effects test facility	104
Cold Leg Intermediate Break Experiment in SPES Facility and Post-Test Calculations with RELAP5 Mod 3.2 Code	84
Natural Circulation of Lead-Bismuth in A-One-Dimensional Loop: Experiments and Code Predictions	77
CATHARE 2 Analysis of the Small Break LOCA Experiment SP-SB-03, Conducted in SPES Facility	73
SIET Experimental Facilities and Testing on LWR Passive Safety Systems	73
LFR-120 Core neutronic verifications	73
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)	71
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics	70
Design, experiments and Relap5 code calculations for the PERSEO facility	69
Theoretical Design and Assessment of Isolation Condenser System Controlled with Thermal Valve Device	68
European Project for Future Advance s in Sciences and Technology for Nuclear Engineering Thermal-Hydraulics (EUROFASTNET)	68
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	68
HE-FUS3 benchmark results	68
The REPAS approach to the evaluation of passive safety systems reliability	67
He-Fus3 Facility Post Test Analysis of Steady State and Transient Experiments with ATHENA Code	65
Investigation of RELAP Capability to Simulate the LBE Cooling System Thermal-Hydraulic	64
Design of the SPES-3 Experimental Facility for the IRIS Reactor Integral Reactor Simulation	63
Rapporto tecnico sulle metodologie di analisi degli eventi esterni e sulla stima del rischio	63
Risk analysis of Nuclear Power Plants against External Events	63
Analysis of Thermal-Hydraulic Performance of IRIS/SPES3 EHRS Condenser with an Appropriate RELAP5 Model	62
SPES3 Integral Tests: Organisation of Facility Analysis and Modelling	62
Analytical Study with the ATHENA Code of the HCPB Blanket Design Experimental Activity on the He-FUS3 Facility	61
Implementation and Preliminary Verification of the RELAP5/PARCS Code for Pb-Bi Cooled Subcritical Systems	61
Overview of the CATHARE Use at ENEA for Innovative Safety Systems	61
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	61
Comparison of Lead-Bismuth and Lead as Coolants for Accelerator Driven Systems	61
SPES 3-IRIS Facility Nodalization for RELAP5 Mod. 3.3 Code and Steady State Qualification	60
RELAP5 assessment on CIRCE decay heat removal experiments	58
Assessment of CATHARE Model of the PERSEO Device on Full-Scale Tests	58
A Neutronics-Thermalhydraulics Model for Preliminary Studies on TRADE Dynamics	57
Benchmark Assessment of Cathare 2 V1.4 on a Loss of Residual Heat Removal System Test Conducted in Bethsy Facility	57
SPES3-IRIS Facility RELAP5 Base Case Transient Analyses for Design Support	57
Pre-Test Analysis for an Experimental Campaign in the Upgraded HE-FUS3 Loop	57
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	56
A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics	56
Benchmarking Activity on ENEA Available Tools for the Dynamic Analysis of LBE Cooled Subcritical Systems	56
In-Vessel Core Retention Strategy (IVCRS)	55
HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis	55
Analytical Assessment of an Enhanced Configuration of Thermal Valve System	55
Influence of the Break Location in the Loss of Coolant Accident Analyses for the ITER Divertor Cooling Loop	54
Final Report on HE-FUS3 Benchmark Exercise	54
Assessment of RELAP5 MOD3.3 and CATHARE2 V1.5A against a Full Scale Test of PERSEO Device	54
Flowblockage accidents in the XADS plant analyzed by means of RELAP5/PARCS	53
Final SI CATHARE ModuleDeliverable D22 of DEEPSSI project	53
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	53
T/H and Transient Analyses to confirm EFIT Preliminary Design	52
Accident Analysis of an Experimental Accelerator Driven System	52
Influence of the Break Location in the Loss of Coolant Accident Analyses for the Iter Divertor Cooling Loop	51
ENEA's Activities on Nuclear Energy	51
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENTAL TESTS AND RELAP5 CODE	51
ENEA's activity in the Safety Analysis of the gas cooled eXperimental Accelerator Driven System (XADS)	51
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	51
Assessment of ATHENA Code Capability to Simulate Helium Cooled Systems for Fusion Reactors	51
The Italian Experience on T/H Best Estimate Codes: Achievements and Perspectives	50
Description of the SI CATHARE module (models, utilisation)Deliverable D23 of DEEPSSI project	50
Analytical assessment of an enhanced configuration of Thermal Valve System	50
Preliminary T/H and Transient Analyses for EFIT Reactor Design	50
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster (BWRCA Project-Contract No. FI4I-CT96-0014)	50
Loss of Coolant Accident in the ITER FW/SB Cooling Loop. A Comparison between ATHENA/INTRA and MELCOR Analyses	49
INVESTIGATION OF RELAP CAPABILITY TO SIMULATE THE LBE COOLING SYSTEM THERMAL-HYDRAULIC	49
BENCHMARKING ACTIVITY ON ENEA AVAILABLE TOOLS FOR THE DYNAMIC ANALYSIS OF LBE COOLED SUBCRITICAL SYSTEMS	49
THERMAL-HYDRAULIC ANALYSIS OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY	49
Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop	49
PERSEO Project: Experimental Facility Set-Up and RELAP5 Code Calculations	48
Sviluppo di un modello numerico per la simulazione del comportamento termoidraulico di un reattore raffreddato a piombo utilizzando il codice RELAP (Parte II)	48
BWR Physics and Thermalhydraulics Complementary Actions to the BWR R&D Cluster(BWRCA project - Contract No. F141-CT96-0014)	47
Thermal-Hydraulic Analysis of the International Fusion Materials Irradiation Facility	47
Simulation of the PANDA Test for the ISP42 Using the CATHARE Code	47
In-Pool Energy Removal System for Emergency Operation: Experimental Tests and RELAP5 Code Calculations	47
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	47
Thermal Valve System for LWR Applications	46
He-FUS3 Facility Nodalization for ATHENA Code	46
INFLUENCE OF THE BREAK LOCATION IN THE LOSS OF COOLANT ACCIDENT ANALYSES FOR THE ITER DIVERTOR COOLING LOOP	46
XADS source transients analyzed by means of RELAP5/PARCS	45
MEGAPIE Post-Test Analysis for the RELAP5 Code Verification	45
SPES3-IRIS facility RELAP5 sensitivity analyses of the Lower Break transient for design support	45
Valutazione e modifica del codice termoidraulico di sistema cathare applicato a metalli liquidi pesanti e ai dati sperimentali del benchmark lacanes	45
Post-Test Calculations with ISAS-ITER Systems for ICE Experiments	45
Application of RELAP5/Mod3 to the Testing of the AP600 Automatic Depressurization System	45
SPES-99 IBLOCA: RELAP5/Mod 3.2 Pre-Test and Post-Test Analysis	44
IFMIF Lithium LOCA Analyses with RELAP5 Code	43
NATURAL CIRCULATION OF LEAD-BISMUTH IN A ONE-DIMENSIONAL LOOP: EXPERIMENTS AND CODE PREDICTIONS	43
Overview of helium cooled system applications with RELAP at ENEA	43
Application of the Capacity Module of the CATHARE Code to the Simulation of Reactor Containment during LOCA	43
Design and Development of a Steam Generator Emergency Feedwater Passive System for Existing and Future PWRs Using Advanced Steam Injectors (DEEPSSI)	43
RELAP5/MOD3 Capability to Simulate the Performance of Isolation Condenser Systems	42
Comparison of RELAP5/MOD3.2 and Cathare VI.3U Post Test Calculations of the BETHSY Test 6.9C	42
PERSEO project: experimental facility set-up and RELAP5 code calculations	42
Evaluation of CATHARE 2 V1.3 Capability to Simulate the Performance of Automatic Depressurization Systems in PWRs	42
IVCRS - Half Yearly Progress Report	41
BWR Physics and Thermalhydraulics Complementary Actions tot he IPSS-BWR R&D Clustei - Final Summary Report	41
CATHARE 2 V 1.4 Capability to Simulate the Performance of ISOLATION CONDENSER SYSTEMS with Thermal Valve	39
Protected and Unprotected Transients for the LBE Cooled eXperimental Accelerator Driven System ENEA's contribution to deliverable 45	39
Preliminary Assessment of an In-Vessel Core Retention Strategy Using Best Estimate Tools	39
SPES 6 Small Break LOCA Post-test Analysis Using CATHARE 2 Code	38
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	38
IN-POOL ENERGY REMOVAL SYSTEM FOR EMERGENCY OPERATION: EXPERIMENT AND ANALYTICAL ASSESSMENT	38
In-Pool Energy Removal System for Emergency Operation: Experiment and Analytical Assessment	38
Totale	5.504

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Categoria	#
all - tutte	46.232
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	46.232

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	62	0	0	0	0	7	5	14	5	3	24	4	0
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	668	20	323	81	98	146	0	0	0	0	0	0	0
Totale													6.066