IRIS
LOMONACO, GUGLIELMO
 Distribuzione geografica
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Continente #
EU - Europa 8.808
Totale 8.808
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Nazione #
IT - Italia 8.808
Totale 8.808
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Città #
Genova 6.334
Vado Ligure 884
Genoa 820
Rapallo 758
Bordighera 12
Totale 8.808
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Nome #
The VHTR and GFR and their use in innovative symbiotic fuel cycles 187
Corrosion issues in high temperature gas cooled reactor (HTR) systems 162
Cross Sections Influence on Monte Carlo Based Burnup Codes Applied to a GFR-like Configuration 152
Initial thermal-hydraulic assessment by OpenFOAM and FLUENT of a subcritical irradiation facility 147
Comparison Among Monte Carlo Based Burnup Codes Applied to the GFR Demonstrator ALLEGRO 143
Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors 141
A low power ADS for transmutation studies in fast systems 137
Partial Redesign of an Accelerator Driven System Target for Optimizing the Heat Removal and Minimizing the Pressure Drops 134
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 129
The Capabilities of HTRs to Burn Actinides and to Optimize Plutonium Exploitation 127
Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up 126
Assessment of a 2D CFD model for a single phase natural circulation loop 124
Numerical investigation of turbulent flow within a channel with chamfered edge ribs in stream-wise direction 123
CFD initial assessment of a protrusions based experimental facility 121
A useful observable for estimating keff in fast subcritical systems 121
Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0© 120
HTGR reactor physics and fuel cycle studies 120
An intrinsically safe facility for forefront research and training on nuclear technologies - Burnup and transmutation 119
Generation IV reactor designs, operation and fuel cycle 118
Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle” 118
A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle 117
A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors 115
An ADS irradiation facility for fast and slow neutrons 114
Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration 112
A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA 112
Preliminary CFD assessment of an experimental test facility operating with heavy liquid metals 112
Nuclear Systems for Hydrogen Production: State of Art and Perspectives in Transport Sector 111
HTR-N Plutonium Cell Burnup Benchmark: Definition, Results Intercomparison 110
Preliminary thermal-fluid-dynamic assessment of an ADS irradiation facility for fast and slow neutrons 109
Innovative Gas-Cooled Reactors 106
Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors 105
New infrastructure for studies of transmutation and fast systems concepts 105
Cross Sections Influence on Monte Carlo Based Burnup Codes 105
Innovative Gas Cooled Reactors 102
HTR Pebble Fuel Burnup Experimental Benchmark 101
THE INFLUENCE OF THE PACKING FACTOR ON THE FUEL TEMPERATURE HOT SPOTS IN A PARTICLE-BED GCFR 98
GCFR coupled neutronic and thermal-fluid-dynamics analyses for a core containing Minor Actinides 97
Contributing to the nuclear 3S's via a methodology aiming at enhancing the synergies between nuclear security and safety 96
CFD preliminary assessment of a protrusions based facility 96
The use of Th in HTR: state of the art and implementation in Th/Pu fuel cycles 95
Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices 93
An In-vivo Comparative Study Between Standard and PET-Based Approach to Assess the Therapeutic Dose in Neutron Capture Therapies 92
Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant 92
Design by theoretical and CFD analyses of a multi-blade screw pump evolving liquid lead for a Generation IV LFR 91
An ADS irradiation facility for fast and slow neutrons 87
Nuclear Desalination: an Alternative Solution to the Water Shortage 84
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 84
A Preliminary Study of an Improved Area Method, Adapted to Short Time Transients in Sub-Critical Systems. 83
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 82
Preliminary Evaluation of a Nuclear Scenario involving Innovative Gas Cooled Reactors 82
PUMA - Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors 80
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 80
Analisi termofludodinamica della configurazione a letto di particelle per un reattore nucleare veloce refrigerato a gas 79
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 79
Waste Radiotoxicity Minimization Using Innovative LWR-HTR-GCFR Symbiotic Fuel Cycles 77
La sistemazione in sicurezza delle scorie nucleari 77
New Developments in Actinides Burning with Symbiotic LWR-HTR-GCFR fuel cycles: perspectives and challenges 76
REFLECTOR EFFECTS ON THE KINETIC RESPONSE IN SUBCRITICAL SYSTEMS 76
Le scorie nucleari: Un problema o una risorsa? - Parte I 73
Assessments of LWR-HTR-GCFR integrated fuel cycle 72
null 68
Development of a Reduced Order Model for Fuel Burnup Analysis 68
THE VALIDATION OF THE TREATMENT PLANNING SYSTEM BDTPS THROUGH AN “IN-VIVO” COMPARISON 67
CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator 67
A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation 66
Preliminary Approach to Sustainable Nuclear Scenario Definition. Case Study: Italy 65
L'Incidente Nucleare di Chernobyl 65
Methods for the assessment of the treatment dose using micro-PET/CT suitable for NCT Treatment Planning Systems in experimental animal models 65
I reattori nucleari ad alta temperatura nella prospettiva energetica futura 65
ANALYSIS OF TRANSITION NUCLEAR FUEL CYCLES 65
A new hybrid fast-slow ADS for research and applications 65
ANALYSIS OF PEBBLE FUELLED ZONE MODELING INFLUENCE ON HTR CORE CALCULATIONS 63
CARL 2.3 63
PU and MA Management in Thermal HTGRs – Impact at Fuel, Reactor and Fuel Cycle levels. 63
Ipotetico Impatto di un aereo di linea su una Centrale Nucleare Esistente 62
PUMA - Plutonium and Minor Actinides management in thermal high-temperature reactors 62
European Programme on High Temperature Reactor Nuclear Physics, Waste and Fuel Cycle Studies 62
Note introduttive sulla Sicurezza Nucleare 61
HTR-N REACTOR PHYSICS AND FUEL CYCLE STUDIES 61
Aspetti di Sicurezza del Reattore EPR 60
Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors - The EU FP6 Project PUMA 60
Classificazione e Sistemazione in Sicurezza delle Scorie Nucleari 59
Myrrha primary heat exchanger tube rupture: Phenomenology and evolution 59
Le scorie nucleari: un falso problema o una vera risorsa? 57
I Reattori Nucleari ad Alta Temperatura (HTR) nella Prospettiva Energetica Futura 57
Nuclear waste impact reduction using multiple fuel recycling strategies 57
Produzione di H2 per Via Nucleare mediante Steam Reforming 56
Reset text 55
THEORETICAL AND NUMERICAL INVESTIGATION OF THREE DESIGNS FOR A PRIMARY CIRCULATION PUMP EVOLVING LIQUID LEAD FOR GEN-IV REACTORS 55
I Veri Costi dell'Energia Nucleare 54
I reattore nucleari a gas ad alta temperatura - Nuovi sviluppi 52
Aspetti Fisici delle Terapie BNCT e GdNCT 51
Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor 51
Calculation tool for heat exchanger tube rupture in pool-type reactors 50
Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review 50
Note sulla Sicurezza Nucleare 49
NUCLEAR WASTE BURNING: AN IMPORTANT GOAL IN THE FRAME OF THE GENERATION IV OF NUCLEAR REACTORS 49
Approaching Nuclear Safety Culture in Fission and Fusion Technology 49
Il Reattore Nucleare Naturale di Oklo 48
Development of CFD models and pre-test calculations for thermal-hydraulics and freezing experiments on Lead coolant 48
Totale 8.775
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Categoria #
all - tutte 28.904
article - articoli 15.981
book - libri 194
conference - conferenze 9.408
curatela - curatele 0
other - altro 2.293
patent - brevetti 0
selected - selezionate 0
volume - volumi 1.028
Totale 57.808
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20201.886 0 0 0 0 0 268 462 141 207 436 273 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
2024/2025993 64 160 94 122 305 248 0 0 0 0 0 0
Totale 9.172