IRIS
LOMONACO, GUGLIELMO
 Distribuzione geografica
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Continente #
EU - Europa 11.690
AS - Asia 1.567
NA - Nord America 1.225
Continente sconosciuto - Info sul continente non disponibili 394
SA - Sud America 128
AF - Africa 18
OC - Oceania 4
Totale 15.026
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Nazione #
IT - Italia 11.421
US - Stati Uniti d'America 1.141
SG - Singapore 580
CN - Cina 404
VN - Vietnam 273
FR - Francia 112
BD - Bangladesh 89
HK - Hong Kong 88
BR - Brasile 85
DE - Germania 35
CA - Canada 29
GB - Regno Unito 26
IN - India 25
FI - Finlandia 23
NL - Olanda 20
AR - Argentina 19
JP - Giappone 17
MX - Messico 17
IQ - Iraq 14
ID - Indonesia 12
RU - Federazione Russa 12
CH - Svizzera 8
EC - Ecuador 8
JM - Giamaica 8
CR - Costa Rica 7
PH - Filippine 7
TW - Taiwan 7
VE - Venezuela 7
SA - Arabia Saudita 6
ES - Italia 5
KE - Kenya 5
KR - Corea 5
NP - Nepal 5
PK - Pakistan 5
PT - Portogallo 5
SV - El Salvador 5
TT - Trinidad e Tobago 5
UA - Ucraina 5
AT - Austria 4
JO - Giordania 4
UZ - Uzbekistan 4
ZA - Sudafrica 4
AU - Australia 3
AZ - Azerbaigian 3
CL - Cile 3
CO - Colombia 3
GT - Guatemala 3
IE - Irlanda 3
MY - Malesia 3
TR - Turchia 3
KZ - Kazakistan 2
LB - Libano 2
LT - Lituania 2
PL - Polonia 2
TH - Thailandia 2
AE - Emirati Arabi Uniti 1
AO - Angola 1
BB - Barbados 1
BG - Bulgaria 1
BS - Bahamas 1
BY - Bielorussia 1
BZ - Belize 1
CG - Congo 1
CI - Costa d'Avorio 1
CY - Cipro 1
DO - Repubblica Dominicana 1
DZ - Algeria 1
EG - Egitto 1
GA - Gabon 1
GE - Georgia 1
GM - Gambi 1
GP - Guadalupe 1
GY - Guiana 1
HN - Honduras 1
HR - Croazia 1
KG - Kirghizistan 1
LC - Santa Lucia 1
LI - Liechtenstein 1
MA - Marocco 1
MD - Moldavia 1
NC - Nuova Caledonia 1
NI - Nicaragua 1
OM - Oman 1
PA - Panama 1
PE - Perù 1
PR - Porto Rico 1
PS - Palestinian Territory 1
SC - Seychelles 1
SE - Svezia 1
SI - Slovenia 1
SY - Repubblica araba siriana 1
UY - Uruguay 1
XK - ???statistics.table.value.countryCode.XK??? 1
Totale 14.633
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Città #
Genova 6.334
Genoa 3.281
Vado Ligure 884
Rapallo 758
San Jose 342
Singapore 267
Lauterbourg 104
Ashburn 98
Ho Chi Minh City 96
Hong Kong 83
Beijing 80
Hanoi 56
Santa Clara 43
New York 32
Frankfurt am Main 30
Helsinki 21
Council Bluffs 20
St Louis 20
Dallas 19
Los Angeles 16
Tokyo 16
Haiphong 14
Milan 13
Rome 13
Bordighera 12
North Charleston 12
Atlanta 11
Boardman 11
Hải Dương 11
Amsterdam 10
Orem 10
Chicago 9
Mexico City 9
Tianjin 9
Buffalo 8
Houston 7
Manchester 7
Shanghai 7
Springfield 7
Zurich 7
Baghdad 6
Biên Hòa 6
Boston 6
Kingston 6
Philadelphia 6
San José 6
Toronto 6
Basingstoke 5
Brasília 5
Brooklyn 5
Carugo 5
City of London 5
Fairfield 5
Flero 5
Florence 5
Jacksonville 5
Montreal 5
Phoenix 5
Seattle 5
São Paulo 5
Amman 4
Bologna 4
Bắc Ninh 4
Curitiba 4
Da Nang 4
Guangzhou 4
Holden 4
Jeddah 4
Livorno 4
Memphis 4
Nairobi 4
Naples 4
Nizhniy Novgorod 4
Princeton 4
San Antonio 4
San Francisco 4
San Salvador 4
Turin 4
Washington 4
Chennai 3
Des Moines 3
Dublin 3
Hackensack 3
Istanbul 3
Jersey City 3
Lisbon 3
Newark 3
Ninh Bình 3
Palermo 3
Phủ Lý 3
Pisa 3
Saint Paul 3
Spokane 3
Sumter 3
Suzhou 3
Taichung 3
Thái Nguyên 3
Baku 2
Banqiao 2
Bari 2
Totale 13.030
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Nome #
The VHTR and GFR and their use in innovative symbiotic fuel cycles 251
A low power ADS for transmutation studies in fast systems 217
Cross Sections Influence on Monte Carlo Based Burnup Codes Applied to a GFR-like Configuration 215
Assessment of a 2D CFD model for a single phase natural circulation loop 215
Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors 209
Initial thermal-hydraulic assessment by OpenFOAM and FLUENT of a subcritical irradiation facility 205
Corrosion issues in high temperature gas cooled reactor (HTR) systems 204
A useful observable for estimating keff in fast subcritical systems 197
Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up 193
Study of an intrinsically safe infrastructure for training and research on nuclear technologies 191
CFD initial assessment of a protrusions based experimental facility 190
Comparison Among Monte Carlo Based Burnup Codes Applied to the GFR Demonstrator ALLEGRO 189
An ADS irradiation facility for fast and slow neutrons 188
A Preliminary Assessment of the Transmutation Potentialities for an ITER-like FW Sector Loaded with MA 185
New infrastructure for studies of transmutation and fast systems concepts 183
A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle 182
Partial Redesign of an Accelerator Driven System Target for Optimizing the Heat Removal and Minimizing the Pressure Drops 180
An intrinsically safe facility for forefront research and training on nuclear technologies - Burnup and transmutation 179
Preliminary thermal-fluid-dynamic assessment of an ADS irradiation facility for fast and slow neutrons 179
A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors 178
Numerical investigation of turbulent flow within a channel with chamfered edge ribs in stream-wise direction 174
Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors 167
CFD preliminary assessment of a protrusions based facility 165
Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration 164
HTGR reactor physics and fuel cycle studies 162
Generation IV reactor designs, operation and fuel cycle 161
Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant 160
An ADS irradiation facility for fast and slow neutrons 158
The Capabilities of HTRs to Burn Actinides and to Optimize Plutonium Exploitation 155
Nuclear Systems for Hydrogen Production: State of Art and Perspectives in Transport Sector 154
Preliminary CFD assessment of an experimental test facility operating with heavy liquid metals 153
An In-vivo Comparative Study Between Standard and PET-Based Approach to Assess the Therapeutic Dose in Neutron Capture Therapies 150
Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle” 150
Simplified models for pebble-bed HTR core burn-up calculations with Monteburns2.0© 150
A Preliminary Study of an Improved Area Method, Adapted to Short Time Transients in Sub-Critical Systems. 149
Design by theoretical and CFD analyses of a multi-blade screw pump evolving liquid lead for a Generation IV LFR 149
Cross Sections Influence on Monte Carlo Based Burnup Codes 148
HTR Pebble Fuel Burnup Experimental Benchmark 143
The use of Th in HTR: state of the art and implementation in Th/Pu fuel cycles 142
Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices 142
Innovative Gas-Cooled Reactors 141
CFD analyses of the internal blockage in the nacie-up fuel Pin Bundle simulator 141
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 139
HTR-N Plutonium Cell Burnup Benchmark: Definition, Results Intercomparison 138
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 138
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 137
A short overview of ITER-like pulsed MCF reactors application as hybrid nuclear systems for actinides transmutation 137
Analisi termofludodinamica della configurazione a letto di particelle per un reattore nucleare veloce refrigerato a gas 135
An Additional Performance of HTRs: the Wastes Radiotoxicity Minimization 135
Innovative Gas Cooled Reactors 131
THE INFLUENCE OF THE PACKING FACTOR ON THE FUEL TEMPERATURE HOT SPOTS IN A PARTICLE-BED GCFR 129
Nuclear Desalination: an Alternative Solution to the Water Shortage 127
A new hybrid fast-slow ADS for research and applications 127
A review of strategies and challenges of super critical water-cooled reactor (SCWR) deployment and technology readiness assessment of a SCWR- SMR design 126
GCFR coupled neutronic and thermal-fluid-dynamics analyses for a core containing Minor Actinides 124
THEORETICAL AND NUMERICAL INVESTIGATION OF THREE DESIGNS FOR A PRIMARY CIRCULATION PUMP EVOLVING LIQUID LEAD FOR GEN-IV REACTORS 123
Novel hybrid pilot experiment proposal for a fusion-fission subcritical coupled system 120
ANALYSIS OF TRANSITION NUCLEAR FUEL CYCLES 116
Contributing to the nuclear 3S's via a methodology aiming at enhancing the synergies between nuclear security and safety 116
Myrrha primary heat exchanger tube rupture: Phenomenology and evolution 115
L'Incidente Nucleare di Chernobyl 113
ANALYSIS OF PEBBLE FUELLED ZONE MODELING INFLUENCE ON HTR CORE CALCULATIONS 112
Assessments of LWR-HTR-GCFR integrated fuel cycle 112
REFLECTOR EFFECTS ON THE KINETIC RESPONSE IN SUBCRITICAL SYSTEMS 112
La sistemazione in sicurezza delle scorie nucleari 108
Development of CFD models and pre-test calculations for thermal-hydraulics and freezing experiments on Lead coolant 108
Classificazione e Sistemazione in Sicurezza delle Scorie Nucleari 107
Preliminary Evaluation of a Nuclear Scenario involving Innovative Gas Cooled Reactors 106
I reattori nucleari ad alta temperatura nella prospettiva energetica futura 105
Development of a Reduced Order Model for Fuel Burnup Analysis 105
PILOT FFHR BASED ON A RFP AS A FUSION CORE 105
Waste Radiotoxicity Minimization Using Innovative LWR-HTR-GCFR Symbiotic Fuel Cycles 103
PUMA - Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors 103
Approaching Nuclear Safety Culture in Fission and Fusion Technology 103
Nuclear Hydrogen Production: Modeling and Preliminary Optimization of a Helical Tube Heat Exchanger 103
Le scorie nucleari: Un problema o una risorsa? - Parte I 101
Aspetti di Sicurezza del Reattore EPR 101
THE VALIDATION OF THE TREATMENT PLANNING SYSTEM BDTPS THROUGH AN “IN-VIVO” COMPARISON 101
New Developments in Actinides Burning with Symbiotic LWR-HTR-GCFR fuel cycles: perspectives and challenges 101
European Programme on High Temperature Reactor Nuclear Physics, Waste and Fuel Cycle Studies 101
CARL 2.3 100
Methods for the assessment of the treatment dose using micro-PET/CT suitable for NCT Treatment Planning Systems in experimental animal models 99
An FMEA Assessment of an HTR-Based Hydrogen Production Plant 98
Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors - The EU FP6 Project PUMA 97
RFP-MSR Hybrid Reactor Model for Tritium Breeding and Actinides Transmutation 96
Note introduttive sulla Sicurezza Nucleare 93
Lattice Boltzmann Method Applied to Nuclear Reactors—A Systematic Literature Review 93
Nuclear waste impact reduction using multiple fuel recycling strategies 92
Preliminary Approach to Sustainable Nuclear Scenario Definition. Case Study: Italy 91
Ipotetico Impatto di un aereo di linea su una Centrale Nucleare Esistente 91
Nuclear Thermal Propulsion for Earth Orbit and Interplanetary Missions: Challenges and Issues 90
I Reattori Nucleari ad Alta Temperatura (HTR) nella Prospettiva Energetica Futura 89
HTR-N REACTOR PHYSICS AND FUEL CYCLE STUDIES 89
A Neutron Source Based on Spherical Tokamak 88
Il Reattore Nucleare Naturale di Oklo 88
PILOT HYBRID EXPERIMENT WITH REVERSED FIELD PINCH AS NEUTRON SOURCE AND DOUBLE FISSION TEST BEDS: AN INNOVATIVE STAGE APPROACH TOWARDS A FULL POWER FUSION-FISSION HYBRID REACTOR 87
Le scorie nucleari: un falso problema o una vera risorsa? 87
Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor 87
PUMA - Plutonium and Minor Actinides management in thermal high-temperature reactors 85
Aspetti Fisici delle Terapie BNCT e GdNCT 84
Totale 13.555
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Categoria #
all - tutte 48.852
article - articoli 26.398
book - libri 443
conference - conferenze 16.452
curatela - curatele 0
other - altro 4.069
patent - brevetti 0
selected - selezionate 0
volume - volumi 1.490
Totale 97.704
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
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
2025/20264.136 473 133 272 377 531 381 653 243 257 339 220 257
2026/2027419 419 0 0 0 0 0 0 0 0 0 0 0
Totale 15.026