IRIS
LOMONACO, GUGLIELMO
 Distribuzione geografica
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Continente #
EU - Europa 11.248
AS - Asia 60
SA - Sud America 39
AF - Africa 1
Totale 11.348
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Nazione #
IT - Italia 11.245
BR - Brasile 36
CN - Cina 35
VN - Vietnam 17
SG - Singapore 3
AR - Argentina 2
BD - Bangladesh 2
NL - Olanda 2
AZ - Azerbaigian 1
EC - Ecuador 1
KZ - Kazakistan 1
RU - Federazione Russa 1
UZ - Uzbekistan 1
ZA - Sudafrica 1
Totale 11.348
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Città #
Genova 6.334
Genoa 3.257
Vado Ligure 884
Rapallo 758
Beijing 21
Bordighera 12
Ho Chi Minh City 10
Hanoi 3
Singapore 3
São Paulo 3
Haiphong 2
Jandira 2
Barnaul 1
Barra Bonita 1
Bonito 1
Botucatu 1
Bragança 1
Brasília 1
Campinas 1
Cape Town 1
Capão da Canoa 1
Cascavel 1
Cornélio Procópio 1
Curitiba 1
Custódia 1
Franca 1
Guarulhos 1
Guayaquil 1
Hortolândia 1
Hughes 1
Huế 1
Ipatinga 1
Jacutinga 1
Jarinu 1
Jatobá 1
Maceió 1
Mogi das Cruzes 1
Mossoró 1
Nawābganj 1
Palhoça 1
Porto Seguro 1
Quixadá 1
Rio Grande 1
Rio de Janeiro 1
Salvador 1
San Justo 1
Sertãozinho 1
Shymkent 1
São Gabriel da Palha 1
Tashkent 1
Valença do Piauí 1
Xique-Xique 1
Totale 11.329
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Nome #
The VHTR and GFR and their use in innovative symbiotic fuel cycles 217
Corrosion issues in high temperature gas cooled reactor (HTR) systems 180
A low power ADS for transmutation studies in fast systems 179
Cross Sections Influence on Monte Carlo Based Burnup Codes Applied to a GFR-like Configuration 178
Initial thermal-hydraulic assessment by OpenFOAM and FLUENT of a subcritical irradiation facility 176
Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors 170
Assessment of a 2D CFD model for a single phase natural circulation loop 167
A useful observable for estimating keff in fast subcritical systems 164
Comparison Among Monte Carlo Based Burnup Codes Applied to the GFR Demonstrator ALLEGRO 163
Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up 161
Partial Redesign of an Accelerator Driven System Target for Optimizing the Heat Removal and Minimizing the Pressure Drops 158
An ADS irradiation facility for fast and slow neutrons 156
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 156
CFD initial assessment of a protrusions based experimental facility 154
A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA 153
An intrinsically safe facility for forefront research and training on nuclear technologies - Burnup and transmutation 151
New infrastructure for studies of transmutation and fast systems concepts 151
Numerical investigation of turbulent flow within a channel with chamfered edge ribs in stream-wise direction 149
A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors 147
Preliminary thermal-fluid-dynamic assessment of an ADS irradiation facility for fast and slow neutrons 145
A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle 142
The Capabilities of HTRs to Burn Actinides and to Optimize Plutonium Exploitation 136
Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors 135
CFD preliminary assessment of a protrusions based facility 134
Generation IV reactor designs, operation and fuel cycle 133
Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration 133
Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0© 131
HTGR reactor physics and fuel cycle studies 131
Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle” 130
Preliminary CFD assessment of an experimental test facility operating with heavy liquid metals 130
The use of Th in HTR: state of the art and implementation in Th/Pu fuel cycles 127
An ADS irradiation facility for fast and slow neutrons 124
Nuclear Systems for Hydrogen Production: State of Art and Perspectives in Transport Sector 123
HTR-N Plutonium Cell Burnup Benchmark: Definition, Results Intercomparison 122
Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant 122
Cross Sections Influence on Monte Carlo Based Burnup Codes 122
Innovative Gas-Cooled Reactors 120
Design by theoretical and CFD analyses of a multi-blade screw pump evolving liquid lead for a Generation IV LFR 120
A Preliminary Study of an Improved Area Method, Adapted to Short Time Transients in Sub-Critical Systems. 118
HTR Pebble Fuel Burnup Experimental Benchmark 118
An In-vivo Comparative Study Between Standard and PET-Based Approach to Assess the Therapeutic Dose in Neutron Capture Therapies 116
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 113
Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices 112
Innovative Gas Cooled Reactors 111
THE INFLUENCE OF THE PACKING FACTOR ON THE FUEL TEMPERATURE HOT SPOTS IN A PARTICLE-BED GCFR 111
Contributing to the nuclear 3S's via a methodology aiming at enhancing the synergies between nuclear security and safety 108
Analisi termofludodinamica della configurazione a letto di particelle per un reattore nucleare veloce refrigerato a gas 107
GCFR coupled neutronic and thermal-fluid-dynamics analyses for a core containing Minor Actinides 106
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 104
Nuclear Desalination: an Alternative Solution to the Water Shortage 103
The GFR in the frame of advanced fuel cycles: the use of DA as an improved way to minimize the MA content in the SNF 103
The use of GFR dedicated assemblies in the frame of advanced symbiotic fuel cycles: an innovative way to minimize the long-term spent fuel radiotoxicity 103
THEORETICAL AND NUMERICAL INVESTIGATION OF THREE DESIGNS FOR A PRIMARY CIRCULATION PUMP EVOLVING LIQUID LEAD FOR GEN-IV REACTORS 101
A new hybrid fast-slow ADS for research and applications 99
A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation 98
La sistemazione in sicurezza delle scorie nucleari 95
ANALYSIS OF TRANSITION NUCLEAR FUEL CYCLES 95
Novel hybrid pilot experiment proposal for a fusion-fission subcritical coupled system 93
Preliminary Evaluation of a Nuclear Scenario involving Innovative Gas Cooled Reactors 92
REFLECTOR EFFECTS ON THE KINETIC RESPONSE IN SUBCRITICAL SYSTEMS 90
Assessments of LWR-HTR-GCFR integrated fuel cycle 89
PUMA - Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors 89
New Developments in Actinides Burning with Symbiotic LWR-HTR-GCFR fuel cycles: perspectives and challenges 88
CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator 88
Waste Radiotoxicity Minimization Using Innovative LWR-HTR-GCFR Symbiotic Fuel Cycles 86
I reattori nucleari ad alta temperatura nella prospettiva energetica futura 85
ANALYSIS OF PEBBLE FUELLED ZONE MODELING INFLUENCE ON HTR CORE CALCULATIONS 84
Le scorie nucleari: Un problema o una risorsa? - Parte I 83
Development of a Reduced Order Model for Fuel Burnup Analysis 83
Nuclear Hydrogen Production: Modeling and Preliminary Optimization of a Helical Tube Heat Exchanger 82
CARL 2.3 81
Aspetti di Sicurezza del Reattore EPR 80
L'Incidente Nucleare di Chernobyl 79
THE VALIDATION OF THE TREATMENT PLANNING SYSTEM BDTPS THROUGH AN “IN-VIVO” COMPARISON 77
Myrrha primary heat exchanger tube rupture: Phenomenology and evolution 77
Approaching Nuclear Safety Culture in Fission and Fusion Technology 77
European Programme on High Temperature Reactor Nuclear Physics, Waste and Fuel Cycle Studies 76
Methods for the assessment of the treatment dose using micro-PET/CT suitable for NCT Treatment Planning Systems in experimental animal models 75
Classificazione e Sistemazione in Sicurezza delle Scorie Nucleari 75
Nuclear waste impact reduction using multiple fuel recycling strategies 74
Preliminary Approach to Sustainable Nuclear Scenario Definition. Case Study: Italy 73
Note introduttive sulla Sicurezza Nucleare 72
Ipotetico Impatto di un aereo di linea su una Centrale Nucleare Esistente 72
PU and MA Management in Thermal HTGRs – Impact at Fuel, Reactor and Fuel Cycle levels. 72
Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors - The EU FP6 Project PUMA 71
PUMA - Plutonium and Minor Actinides management in thermal high-temperature reactors 70
HTR-N REACTOR PHYSICS AND FUEL CYCLE STUDIES 70
Le scorie nucleari: un falso problema o una vera risorsa? 68
Development of CFD models and pre-test calculations for thermal-hydraulics and freezing experiments on Lead coolant 68
null 68
I Reattori Nucleari ad Alta Temperatura (HTR) nella Prospettiva Energetica Futura 66
Calculation tool for heat exchanger tube rupture in pool-type reactors 66
Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review 66
Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor 65
Produzione di H2 per Via Nucleare mediante Steam Reforming 64
Aspetti Fisici delle Terapie BNCT e GdNCT 64
I Veri Costi dell'Energia Nucleare 63
Il Reattore Nucleare Naturale di Oklo 62
I reattore nucleari a gas ad alta temperatura - Nuovi sviluppi 61
Reset text 61
Totale 10.856
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Categoria #
all - tutte 39.755
article - articoli 21.615
book - libri 306
conference - conferenze 13.291
curatela - curatele 0
other - altro 3.251
patent - brevetti 0
selected - selezionate 0
volume - volumi 1.292
Totale 79.510
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021535 0 0 0 0 44 58 45 44 58 66 134 86
2021/20221.152 21 97 88 104 42 84 63 291 78 119 32 133
2022/2023940 82 67 15 78 126 154 12 86 186 14 105 15
2023/2024586 48 87 11 71 38 140 34 22 26 15 30 64
2024/20252.292 64 160 94 122 305 259 281 349 78 107 249 224
2025/20261.259 473 133 272 377 4 0 0 0 0 0 0 0
Totale 11.730