statistiche ricercatore

BANDINI, GIACOMINO

Distribuzione geografica

Continente	#
NA - Nord America	2.504
EU - Europa	1.418
AS - Asia	411
Continente sconosciuto - Info sul continente non disponibili	16
OC - Oceania	10
AF - Africa	7
SA - Sud America	5
Totale	4.371

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Nazione	#
US - Stati Uniti d'America	2.216
GB - Regno Unito	496
SE - Svezia	403
CA - Canada	284
IT - Italia	181
HK - Hong Kong	173
CN - Cina	146
DE - Germania	137
FR - Francia	47
BE - Belgio	43
FI - Finlandia	43
IN - India	34
VN - Vietnam	21
RU - Federazione Russa	18
AT - Austria	17
EU - Europa	14
SG - Singapore	14
JP - Giappone	9
IE - Irlanda	7
AU - Australia	6
BR - Brasile	5
RO - Romania	5
DZ - Algeria	4
ID - Indonesia	4
MX - Messico	4
NL - Olanda	4
NZ - Nuova Zelanda	4
UA - Ucraina	4
ES - Italia	3
HU - Ungheria	3
IR - Iran	3
KR - Corea	3
A1 - Anonimo	2
BG - Bulgaria	2
CZ - Repubblica Ceca	2
TW - Taiwan	2
CI - Costa d'Avorio	1
LU - Lussemburgo	1
NG - Nigeria	1
NO - Norvegia	1
PH - Filippine	1
SI - Slovenia	1
SN - Senegal	1
TR - Turchia	1
Totale	4.371

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Città	#
Chandler	880
San Mateo	280
Southend	280
Toronto	275
Ashburn	140
Berlin	95
Boardman	91
New York	58
Redwood City	46
Helsinki	43
Las Vegas	43
Mountain View	43
Brussels	42
Beijing	41
Hong Kong	35
Marseille	35
Washington	32
Ann Arbor	28
Rome	22
Bologna	21
Trenton	19
Dong Ket	17
Central	16
Los Angeles	16
Miami	16
Rockville	12
Tong	12
Vienna	11
Guangzhou	10
Shanghai	10
Milan	8
Borås	7
Dublin	6
Singapore	6
Xian	5
Arona	4
Hanoi	4
Jakarta	4
Karlsruhe	4
Mazzano Romano	4
Mioveni	4
Norwalk	4
Ottawa	4
Salerno	4
San Vito Lo Capo	4
Turin	4
Wuhan	4
Aubervilliers	3
Budapest	3
Central District	3
Florence	3
Kula	3
Moscow	3
São Paulo	3
Tokyo	3
Auckland	2
Bangalore	2
Brisbane	2
Cincinnati	2
Duncan	2
Formello	2
Genoa	2
Grosseto	2
Jinan	2
Kowloon	2
Kumar	2
L'Arboc	2
Melbourne	2
Nanjing	2
New Delhi	2
Palermo	2
Partinico	2
Pietrasanta	2
Podolsk	2
Potenza	2
Redmond	2
Serra	2
Shenzhen	2
Sofia	2
Taipei	2
Trebic	2
Trieste	2
Abidjan	1
Abuja	1
Afragola	1
Albuquerque	1
Barrington	1
Blackrock	1
Buffalo	1
Canale Monterano	1
Caserta	1
Castenaso	1
Cavaillon	1
Cessnock	1
Changsha	1
Chengdu	1
Chennai	1
Chongqing	1
Civitavecchia	1
Colombes	1
Totale	2.845

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Nome	#
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment	177
Report on the Results of Analysis of DEC Events for the ETDR (ALFRED)	100
Analysis of B9+ PHEBUS SFD Experiment with ICARE2 and SCDAP/RELAP 5 Codes	74
Calcoli e validazioni relativi ai codici di calcolo specifici per l’analisi degli incidenti gravi	73
Analysis of SCARABEE BE+3 experiment with ASTEC-Na and comparison with other SFR safety analysis codes	68
ENEA activity in CESAM Project	66
Development and Verification of Calculation Models for the Accident Analysis in Nuclear Power Plants	66
Analysis of PHEBUS FP and QUENCH Tests with ICARE2 Code and Comparison with SCDAP/RELAP5 Code Results	61
ENEA contribution to the “Final report on system code assessment for HLM system dynamics”	60
ASTEC validation on TMI-2 and LOFT LP-FP-2	58
ENEA-PISA University Contribution to the Reinforced Concerted Action Final Report Core Degradation. Core Severe Damage Modeling	58
Contributo ENEA al: 600 MWth MARS Nuclear Power Plant, Design Progress Report 1997	58
Raman/XRF/EDX microanalysis of 2nd-century stuccoes from Domus Valeriorum in Rome	57
FP7-Maxsima work package 2 "safety analysis in support of myrrha" main outcome and conclusions	56
Post-test of the sgtr experimental tests carried out in the LIFUS facility	56
Assessment of ASTEC-Na Thermal-Hydraulic Models on Experiments and Benchmarking with Other Codes	56
ENEA Activities in the First 6 Months of 1998	55
Assessment of the enhanced DHRS configuration for MYRRHA reactor	54
Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling	53
Calculation of the PWR-1300 H3 Sequence with ASTEC V1.2 Code and Comparison with CATHARE2 V2.5 Code	53
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation	52
Investigation of Core Degradation (COBE). Final Report	52
Post-Test Analysis of QUENCH-11 Experiment with ICARE/CATHARE Code	52
Assessment of PWR cores behavior and estimate of confidence level got with the use of mechanistic and / or integral codes calculations of accident sequences with reference to TMI-2 reactor	52
Use of a Multichannel Flow Model in SCDAP/RELAP5 Analysis for FPT0	51
Analysis of the ZrO2 Layer Chemical Stability in Zry Cladding above Zry Melting Point. Definition and Validation of a ZrO2 Failure Criterion to be Implemented in the Core Degradation Codes	51
Analysis of the OECD LOFT Fission Product Experiment LP-FP-2 with ASTEC VI .2.1 Code	51
Lessons Learned from the Result Comparison of Calculations of a Reference Severe Accident Sequence on a TMI-2 Like PWR Reactor of 900 MWe with the Integral Codes ASTEC and MELCOR	51
LBE-Water Interaction in Sub-Critical Reactors: First Experimental and Modelling Results	50
Calculation of the Phase 1 of TMI -2 Accident with ASTEC V1 Code	50
Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors	49
Molten Material Relocation into the Lower Plenum: a Status Report	49
Benchmark on Thermo-Fluid Dynamics of an Open Square Lattice Core of a Lead Cooled Reactor with SIMMER-III and FEM-LCORE Codes	49
First analysis of AGS0, LT2 and E9 cabri tests with the new SFR safety code ASTEC-Na	49
Safety studies for the MYRRHA critical core with the SIMMER-III code	48
Investigation of Core Degradation	48
Analyses of an unmitigated station blackout transient with ASTEC, MAAP and MELCOR Codes	48
In-Vessel Core Retention Strategy (IVCRS)	47
TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5	47
W-DHR Testing in CIRCE Facility - RELAP5/Mod3.3 Pre.Test Calculations	47
ENEA Activities in the Last 6 Months of 1998	47
Core loss during a severe accident (COLOSS)	46
RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments	46
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients	46
Loss of core integrity in a LFR system: models and preliminary numerical analysis	46
T/H and Transient Analyses to confirm EFIT Preliminary Design	45
Analysis or AEKI PWR Fuel Rod Dissolution Tests with ICARE/CATHARE andSCDAP/RELAP5 CodesAuthors: G. Bandini, S. Ederli(SAM-COLOSS-PO72 Part - A)	45
Main Specific Safety Phenomena for the LBE-Cooled XADS	45
Validation of CESAR Thermal-Hydraulic Module of ASTEC V1.2 Code on BETHSY Experiments	45
Unlimited Cooling Capacity of the Passive-Type Emergency Core Cooling System of the Mars Reactor	45
Fuel dispersion and flow blockage analyses for the Myrrha-Fastef reactor by simmer code	43
Intermediate Analysis Report of PHEBUS FP Test FPT-0: Bundle Degradation and Release	43
Interpretation of TRIGA Experimental Data with SIMMER-III Code for RELAP5 Model Evaluation and Transient Analysis	43
Code assessment and modelling for Design Basis Accident Analysis of the European sodium fast reactor design. Part I: System description, modelling and benchmarking	42
Analysis of QUENCH-O9 Test with ICARE/CATHARE Code(SAM-COLOSS-PO71 - Part B)	42
Analysis of Bethsy Experiment 4.3b with ASTEC VI .2 Code for CESAR Thermal-Hydraulic Module Validation	42
Preliminary T/H and Transient Analyses for EFIT Reactor Design	42
TMI-2 Accident Analysis with SCDAP/RELAP5 Code	42
Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis	41
Single and two-phase sodium flow analysis for two tucop cabri tests using the ASTEC-Na code	41
Bundle Calculations for PHEBUS FPT0 Test Using SCDAP/RELAP5	41
ICARE/CATHARE Calculation of the QUENCH-11 Experiment in the Frame of the IRSN Participation in the SARNET Benchmark	40
Tridimensional analysis of local perturbations on the core reactivity and the thermal-hydraulics of the fuel elements	40
European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems	39
JASMIN Project: Minutes of the WP2.1 Technical Meeting ENEA/Bologna, 21-22 July 2014	39
Review of heat transfer and pressure drop correlations for liquid metal in T/H system codes	39
PHEBUS FPT-1 Benchmark: ENEA Calculations with SCDAP/RELAP5 and ICARE2 Codes	39
Ex-vessel core melt stabilization research (ECOSTAR)	38
Ex-vessel core melt stabilization research (ECOSTAR)	38
RELAP5 assessment on CIRCE decay heat removal experiments	38
PHEBUS FPT0: Bundle Calculations for the Reference Scenario	38
FPT0 Bundle Calculation: ICARE2 V2 Mod1 and SCDAP/RELAP5 Mod2 Comparison	38
Core loss during a severe accident (COLOSS)	37
Overview of the independent ASTEC V2.0 validation by SARNET partners	37
Post-Test Calculations for the QUENCH-01 Experiment with ICARE2 and SCDAP/RELAP5 Codes	37
Sviluppo e validazione di metodi e strumenti per le analisi di sicurezza: Modellistica e codici per l’analisi di incidenti severi	36
Investigation of Core Degradation (COBE)	36
FPT0 Molten Pool Analysis with SCDAP/RELAP5/MOD3.1 Code	35
Ex-Vessel Core Melt Stabilization Research (ECOSTAR)	35
Accident Control Mechanisms/Safety Limits	35
Thermal-Hydraulics of Corium Pools	34
Preliminary Calculation of the Phase 2 of TMI-2 Accident with ASTEC V1 Code	34
ICARE2 and SCDAP/RELAP5 Result Comparison in the Post-Test Analysis of PHEBUS FPT1 Test	34
Core Loss During a Severe Accident (COLOSS)	33
Preliminary Assessment of the DIVER Concept Using Best Estimate Tools	32
Post-Test Analysis for PHEBUS FPT0 Experiment with SCADP/RELAP5/MOD3.1 Code	32
TIM-2 Accident Analysis with ASTEC V1 Code	32
Transient analyses for the MYRRHA-FASTEF reactor by simmer code	32
Implementation and qualification of pool models in system codes	31
Core Degradation and Hydrogen Generation in the TMI-2 Accident with SCDAP/RELAP5	30
Pre-Test Analysis for PHEBUS FPT1 Experiment with SCADP/RELAP5/MOD3.1 Code	29
TMI-2 Accident Analysis:2nd 8et of ICARE/CATHARE and ASTEC VI Calculations(SAM-COLOSS-P037 - Part A,B)	26
Interpretation of TRIGA Experimental Data with SIMMER-III Code forRELAP5 Model Evaluation and Transient Analysis	21
Totale	4.384

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Categoria	#
all - tutte	30.374
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	30.374

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	Totale	Lug	Ago	Sett	Ott	Nov	Dic	Gen	Feb	Mar	Apr	Mag	Giu
2019/2020	83	0	0	0	0	5	17	7	21	10	12	7	4
2020/2021	681	8	8	5	16	189	11	7	70	38	31	273	25
2021/2022	979	26	283	26	68	110	19	31	249	26	8	62	71
2022/2023	1.806	113	350	129	206	98	307	4	122	357	42	43	35
2023/2024	835	51	49	150	23	107	175	39	82	73	49	37	0
Totale													4.384