LOMONACO, GUGLIELMO
 Distribuzione geografica
Continente #
EU - Europa 8.273
Totale 8.273
Nazione #
IT - Italia 8.273
Totale 8.273
Città #
Genova 6.334
Rapallo 758
Genoa 754
Vado Ligure 415
Bordighera 12
Totale 8.273
Nome #
The VHTR and GFR and their use in innovative symbiotic fuel cycles 183
Corrosion issues in high temperature gas cooled reactor (HTR) systems 155
Cross Sections Influence on Monte Carlo Based Burnup Codes Applied to a GFR-like Configuration 149
Initial thermal-hydraulic assessment by OpenFOAM and FLUENT of a subcritical irradiation facility 140
Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors 137
Comparison Among Monte Carlo Based Burnup Codes Applied to the GFR Demonstrator ALLEGRO 136
Partial Redesign of an Accelerator Driven System Target for Optimizing the Heat Removal and Minimizing the Pressure Drops 128
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 125
Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up 123
The Capabilities of HTRs to Burn Actinides and to Optimize Plutonium Exploitation 122
Numerical investigation of turbulent flow within a channel with chamfered edge ribs in stream-wise direction 118
A useful observable for estimating keff in fast subcritical systems 118
HTGR reactor physics and fuel cycle studies 117
Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle” 116
Assessment of a 2D CFD model for a single phase natural circulation loop 116
A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle 114
Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0© 114
CFD initial assessment of a protrusions based experimental facility 114
A low power ADS for transmutation studies in fast systems 113
Generation IV reactor designs, operation and fuel cycle 112
An intrinsically safe facility for forefront research and training on nuclear technologies - Burnup and transmutation 111
A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors 109
A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA 108
HTR-N Plutonium Cell Burnup Benchmark: Definition, Results Intercomparison 107
Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration 107
Nuclear Systems for Hydrogen Production: State of Art and Perspectives in Transport Sector 107
An ADS irradiation facility for fast and slow neutrons 107
Preliminary CFD assessment of an experimental test facility operating with heavy liquid metals 106
Preliminary thermal-fluid-dynamic assessment of an ADS irradiation facility for fast and slow neutrons 105
Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors 102
Cross Sections Influence on Monte Carlo Based Burnup Codes 102
Innovative Gas-Cooled Reactors 101
New infrastructure for studies of transmutation and fast systems concepts 101
Innovative Gas Cooled Reactors 98
HTR Pebble Fuel Burnup Experimental Benchmark 96
THE INFLUENCE OF THE PACKING FACTOR ON THE FUEL TEMPERATURE HOT SPOTS IN A PARTICLE-BED GCFR 95
GCFR coupled neutronic and thermal-fluid-dynamics analyses for a core containing Minor Actinides 93
Contributing to the nuclear 3S's via a methodology aiming at enhancing the synergies between nuclear security and safety 92
CFD preliminary assessment of a protrusions based facility 91
The use of Th in HTR: state of the art and implementation in Th/Pu fuel cycles 90
Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices 89
An In-vivo Comparative Study Between Standard and PET-Based Approach to Assess the Therapeutic Dose in Neutron Capture Therapies 88
Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant 87
Design by theoretical and CFD analyses of a multi-blade screw pump evolving liquid lead for a Generation IV LFR 84
An ADS irradiation facility for fast and slow neutrons 83
Nuclear Desalination: an Alternative Solution to the Water Shortage 79
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 79
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 78
A Preliminary Study of an Improved Area Method, Adapted to Short Time Transients in Sub-Critical Systems. 78
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 76
PUMA - Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors 75
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 75
Preliminary Evaluation of a Nuclear Scenario involving Innovative Gas Cooled Reactors 75
Waste Radiotoxicity Minimization Using Innovative LWR-HTR-GCFR Symbiotic Fuel Cycles 74
Analisi termofludodinamica della configurazione a letto di particelle per un reattore nucleare veloce refrigerato a gas 74
La sistemazione in sicurezza delle scorie nucleari 73
New Developments in Actinides Burning with Symbiotic LWR-HTR-GCFR fuel cycles: perspectives and challenges 73
REFLECTOR EFFECTS ON THE KINETIC RESPONSE IN SUBCRITICAL SYSTEMS 71
Assessments of LWR-HTR-GCFR integrated fuel cycle 68
null 67
Le scorie nucleari: Un problema o una risorsa? - Parte I 64
THE VALIDATION OF THE TREATMENT PLANNING SYSTEM BDTPS THROUGH AN “IN-VIVO” COMPARISON 64
Development of a Reduced Order Model for Fuel Burnup Analysis 64
I reattori nucleari ad alta temperatura nella prospettiva energetica futura 62
CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator 62
L'Incidente Nucleare di Chernobyl 61
A new hybrid fast-slow ADS for research and applications 60
Preliminary Approach to Sustainable Nuclear Scenario Definition. Case Study: Italy 59
PUMA - Plutonium and Minor Actinides management in thermal high-temperature reactors 59
CARL 2.3 59
Methods for the assessment of the treatment dose using micro-PET/CT suitable for NCT Treatment Planning Systems in experimental animal models 59
ANALYSIS OF TRANSITION NUCLEAR FUEL CYCLES 59
Ipotetico Impatto di un aereo di linea su una Centrale Nucleare Esistente 58
ANALYSIS OF PEBBLE FUELLED ZONE MODELING INFLUENCE ON HTR CORE CALCULATIONS 58
A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation 58
European Programme on High Temperature Reactor Nuclear Physics, Waste and Fuel Cycle Studies 58
Aspetti di Sicurezza del Reattore EPR 56
Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors - The EU FP6 Project PUMA 56
HTR-N REACTOR PHYSICS AND FUEL CYCLE STUDIES 56
Note introduttive sulla Sicurezza Nucleare 55
PU and MA Management in Thermal HTGRs – Impact at Fuel, Reactor and Fuel Cycle levels. 55
Classificazione e Sistemazione in Sicurezza delle Scorie Nucleari 55
Myrrha primary heat exchanger tube rupture: Phenomenology and evolution 54
I Reattori Nucleari ad Alta Temperatura (HTR) nella Prospettiva Energetica Futura 53
Nuclear waste impact reduction using multiple fuel recycling strategies 53
Le scorie nucleari: un falso problema o una vera risorsa? 52
Produzione di H2 per Via Nucleare mediante Steam Reforming 52
Reset text 51
THEORETICAL AND NUMERICAL INVESTIGATION OF THREE DESIGNS FOR A PRIMARY CIRCULATION PUMP EVOLVING LIQUID LEAD FOR GEN-IV REACTORS 51
I reattore nucleari a gas ad alta temperatura - Nuovi sviluppi 48
I Veri Costi dell'Energia Nucleare 48
Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor 48
Aspetti Fisici delle Terapie BNCT e GdNCT 47
Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review 47
NUCLEAR WASTE BURNING: AN IMPORTANT GOAL IN THE FRAME OF THE GENERATION IV OF NUCLEAR REACTORS 46
Calculation tool for heat exchanger tube rupture in pool-type reactors 45
Il Reattore Nucleare Naturale di Oklo 44
Novel hybrid pilot experiment proposal for a fusion-fission subcritical coupled system 44
Note sulla Sicurezza Nucleare 43
Il futuro passa dalle esportazioni 43
Totale 8.290
Categoria #
all - tutte 27.446
article - articoli 15.229
book - libri 186
conference - conferenze 8.874
curatela - curatele 0
other - altro 2.167
patent - brevetti 0
selected - selezionate 0
volume - volumi 990
Totale 54.892


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20202.086 0 0 0 0 200 268 462 141 207 436 273 99
2020/2021721 38 50 53 45 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
2024/2025452 64 160 94 122 12 0 0 0 0 0 0 0
Totale 8.631