PORTO @ Archivio Istituzionale della Ricerca

RAVETTO, PIERO
 Distribuzione geografica
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Continente #
NA - Nord America 29.595
EU - Europa 24.787
AS - Asia 14.372
SA - Sud America 1.593
Continente sconosciuto - Info sul continente non disponibili 259
AF - Africa 192
OC - Oceania 8
Totale 70.806
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Nazione #
US - Stati Uniti d'America 29.018
IT - Italia 6.815
GB - Regno Unito 4.086
CN - Cina 3.923
DE - Germania 3.873
SG - Singapore 3.859
FR - Francia 3.504
VN - Vietnam 2.883
UA - Ucraina 1.853
RU - Federazione Russa 1.469
BR - Brasile 1.292
KR - Corea 862
TR - Turchia 683
HK - Hong Kong 551
IE - Irlanda 539
SE - Svezia 482
CH - Svizzera 466
NL - Olanda 442
IN - India 436
FI - Finlandia 375
CA - Canada 330
JP - Giappone 203
BE - Belgio 183
AT - Austria 182
BD - Bangladesh 160
AR - Argentina 123
AE - Emirati Arabi Uniti 122
MX - Messico 96
PH - Filippine 85
TH - Thailandia 83
ES - Italia 79
TW - Taiwan 74
IQ - Iraq 72
PK - Pakistan 63
IR - Iran 62
ID - Indonesia 59
AP - ???statistics.table.value.countryCode.AP??? 55
RO - Romania 43
EC - Ecuador 42
EU - Europa 41
MY - Malesia 41
CO - Colombia 40
IL - Israele 40
CL - Cile 34
PL - Polonia 33
SA - Arabia Saudita 32
JM - Giamaica 31
CZ - Repubblica Ceca 29
ZA - Sudafrica 29
CR - Costa Rica 27
UZ - Uzbekistan 27
SN - Senegal 25
NG - Nigeria 24
VE - Venezuela 24
EG - Egitto 23
PT - Portogallo 20
JO - Giordania 18
NO - Norvegia 18
PY - Paraguay 17
SI - Slovenia 17
DK - Danimarca 16
EE - Estonia 16
LU - Lussemburgo 16
MA - Marocco 16
BY - Bielorussia 15
CI - Costa d'Avorio 15
GT - Guatemala 15
NI - Nicaragua 15
AZ - Azerbaigian 14
TN - Tunisia 14
BG - Bulgaria 13
PE - Perù 13
KE - Kenya 12
NP - Nepal 12
HU - Ungheria 11
PR - Porto Rico 11
SV - El Salvador 11
KZ - Kazakistan 10
SK - Slovacchia (Repubblica Slovacca) 10
TT - Trinidad e Tobago 10
HN - Honduras 9
LT - Lituania 9
AU - Australia 8
DO - Repubblica Dominicana 8
DZ - Algeria 7
KG - Kirghizistan 7
SY - Repubblica araba siriana 7
GR - Grecia 6
HR - Croazia 6
OM - Oman 6
UY - Uruguay 6
AL - Albania 5
PS - Palestinian Territory 5
AO - Angola 4
BA - Bosnia-Erzegovina 4
ET - Etiopia 4
LV - Lettonia 4
PA - Panama 4
AM - Armenia 3
BB - Barbados 3
Totale 70.497
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Città #
Ashburn 7.171
Southend 3.641
Seattle 2.986
Singapore 2.045
San Jose 1.525
Beijing 1.291
Chandler 1.250
Fairfield 1.095
Turin 1.042
Council Bluffs 1.012
Princeton 925
Jacksonville 896
Ho Chi Minh City 725
Hanoi 692
Ann Arbor 626
Woodbridge 569
Berlin 556
Santa Clara 556
Milan 530
Dublin 529
Izmir 513
San Ramon 490
Cambridge 470
Torino 457
Wilmington 457
Houston 456
Chicago 440
Boardman 420
Hong Kong 415
Bern 407
Shanghai 406
Zhengzhou 403
Helsinki 312
San Donato Milanese 273
Los Angeles 265
Lauterbourg 258
Seoul 255
Baltimore 235
Dallas 229
Pennsylvania Furnace 219
Zaporozhye 219
Rome 212
Overberg 206
San Mauro Torinese 176
Bologna 158
Vienna 156
Hefei 152
Da Nang 143
Saint Petersburg 141
Putian 139
Haiphong 132
New York 125
Brussels 121
Mountain View 112
Redwood City 107
Monopoli 104
São Paulo 102
Abu Dhabi 97
Moscow 95
Phoenix 95
Buffalo 90
Toronto 84
Padua 80
Guangzhou 78
Gif-sur-yvette 77
Hangzhou 66
Atlanta 65
Paris 63
Tokyo 63
Frankfurt am Main 62
Genoa 61
Washington 61
Munich 59
Bremen 58
Columbus 58
Malatya 57
North Bergen 56
San Diego 56
Orem 54
Modena 52
Norwalk 52
The Dalles 52
London 51
Porto Alegre 50
Montreal 46
Palermo 46
Pisa 46
Amsterdam 45
Changsha 45
Miano 45
Piscataway 43
Bangkok 41
San Francisco 40
Melun 39
Yubileyny 38
Can Tho 37
Shenzhen 35
Ankara 34
Genova 34
Strasbourg 34
Totale 41.987
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Nome #
A tribute to Bruno Montagnini, Professor of Nuclear Reactor Physics, University of Pisa 811
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 726
Study of a low-power, fast-neutron-based ADS 471
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 460
PROPOSAL FOR THE UTILIZATION OF HONEY BEE AS AN EFFICIENT INDICATOR OF RADIACTIVE CONTAMINATION 458
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 438
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 434
A method for on-line reactivity monitoring in nuclear reactors 434
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 425
A method for the continuous monitoring of reactivity in subcritical source-driven systems 420
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 413
Assessment of an on-line reactivity monitoring technique 412
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 408
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 405
Assessment of the performance of the spectral element method applied to neutron transport problems 399
Alternative definitions of kinetic parameters for accelerator driven systems 386
Neutronic Evaluations for the EVOL Molten Salt Reactor 378
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 375
Integral parameters in source-driven systems 374
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 372
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 369
Integral neutron transport and new computational methods: a review 357
SP2 – Asymptotic P1 Equivalence 355
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 355
Implementation of the quasi-static method for neutron transport 354
Reflector effects on the kinetic response in subcritical systems 354
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 346
Evaluation of Ray Effects in Linear Transport Problems 344
On the relation between spherical harmonics and simplified spherical harmonics methods 342
Alternative factorization methods for reactor kinetics 339
Evaluation of ray effects in linear transport problems 336
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 335
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 335
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 335
Development of dynamic models for neutron transport calculations 330
An Approximate Method to Study the One-Velocity Neutron Integral Transport Equation 330
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 329
Kinetics of a Point Reactor in the Presence of Reactivity Oscillations 325
The adjoint neutron transport equation and the statistical approach for its solution 322
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 322
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 321
Random effects on reactivity in molten salt reactors 318
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 317
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 316
A method for reactivity monitoring in subcritical source-driven systems 316
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 315
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 314
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 314
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 313
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 310
Coupled dynamics in the physics of molten salt reactors 308
On the spectrum of the multigroup diffusion equations 307
SPECIAL ISSUE: IN HONOUR OF PROFESSOR BRUNO MONTAGNINI 305
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 303
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 303
Advanced Computational Models for Accelerator-Driven Systems 302
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 301
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 300
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 299
XXI International Conference on Transport Theory 299
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 299
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 298
Computational Methods for Multidimensional Neutron Diffusion Problems 298
Assessment of a new method for reactivity measurement 296
Some dynamic A-n, S-2n analytic calculations 294
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 292
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 288
Some Features of Spatial Neutron Kinetics for Multiplying Systems 287
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 286
Application of a Numerical Laplace Transform Inversion Technique to a Problem in Reactor Dynamics 286
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 284
Development of dynamic models for neutron transport calculations 283
Alternative Forms of the Time-Dependent Neutron Transport Equation 283
Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems 282
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 281
Analytical approach to the neutron kinetics of the non-homogeneous reactor 281
Random Effects of Fissile Lumps in Molten Salt Reactors 280
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 276
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 276
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 275
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 275
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 273
Basic Reactor Physics Problems in Fluid-Fuel Recirculated Reactors 271
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 271
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 270
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 269
On the importance of effective convergence velocity of synthetic acceleration methods in neutron transport 269
Angular Finite Element Techniques in Neutron Transport 269
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 269
The time-dependent P1 model for the neutronics of multiplying systems: a review 267
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 267
Analysis of the Evolution of Perturbations in a Magnetized Collisionless Plasma with an Integral-Equation Technique 263
the An method and the Spherical harmonics approximation in neutron transport theory 263
An alternative formulation of the monokinetic transport equation 262
The quasi-static method revisited 261
Variable grid finite difference methods for study of longitudinally varying planar waveguides 260
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems” 259
Three-Dimensional Neutron Analysis of Accelerator-Driven Systems 259
Solution of 3D multigroup, linearly anisotropic scattering, criticality problems by the AN boundary-element response-matrix method 258
Simplified PN and AN methods in Neutron Transport 258
Totale 33.032
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Categoria #
all - tutte 205.570
article - articoli 96.176
book - libri 0
conference - conferenze 102.744
curatela - curatele 2.535
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 3.081
Totale 410.106
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20221.979 0 0 0 94 93 132 83 103 78 132 444 820
2022/20234.579 578 840 143 405 424 622 293 242 345 40 179 468
2023/20241.568 75 306 68 62 115 113 44 64 89 106 123 403
2024/20256.140 157 983 514 611 396 432 319 389 807 409 523 600
2025/202614.267 832 783 914 1.426 978 841 2.151 982 3.065 1.483 266 546
2026/20273.702 422 356 1.194 1.730 0 0 0 0 0 0 0 0
Totale 70.806