RAVETTO, PIERO
 Distribuzione geografica
Continente #
NA - Nord America 26.751
EU - Europa 24.306
AS - Asia 14.281
SA - Sud America 1.536
AF - Africa 191
OC - Oceania 7
Continente sconosciuto - Info sul continente non disponibili 4
Totale 67.076
Nazione #
US - Stati Uniti d'America 26.415
IT - Italia 6.332
GB - Regno Unito 4.086
CN - Cina 3.930
DE - Germania 3.881
SG - Singapore 3.827
FR - Francia 3.510
VN - Vietnam 2.891
UA - Ucraina 1.861
RU - Federazione Russa 1.473
BR - Brasile 1.261
KR - Corea 864
TR - Turchia 683
HK - Hong Kong 551
IE - Irlanda 541
SE - Svezia 484
CH - Svizzera 465
NL - Olanda 441
IN - India 436
FI - Finlandia 376
JP - Giappone 195
CA - Canada 194
AT - Austria 182
BE - Belgio 182
AE - Emirati Arabi Uniti 120
AR - Argentina 120
BD - Bangladesh 106
MX - Messico 88
PH - Filippine 85
TH - Thailandia 82
TW - Taiwan 75
IQ - Iraq 72
ES - Italia 71
IR - Iran 62
PK - Pakistan 62
AP - ???statistics.table.value.countryCode.AP??? 55
ID - Indonesia 53
EU - Europa 41
MY - Malesia 41
RO - Romania 41
IL - Israele 40
EC - Ecuador 36
CO - Colombia 33
PL - Polonia 31
CL - Cile 30
SA - Arabia Saudita 30
ZA - Sudafrica 29
CZ - Repubblica Ceca 28
UZ - Uzbekistan 26
SN - Senegal 25
NG - Nigeria 24
EG - Egitto 23
PT - Portogallo 20
VE - Venezuela 20
JO - Giordania 18
NO - Norvegia 17
DK - Danimarca 16
MA - Marocco 16
PY - Paraguay 16
BY - Bielorussia 15
CI - Costa d'Avorio 15
LU - Lussemburgo 15
AZ - Azerbaigian 14
SI - Slovenia 14
TN - Tunisia 14
BG - Bulgaria 13
JM - Giamaica 12
KE - Kenya 12
NP - Nepal 12
PE - Perù 12
HU - Ungheria 11
EE - Estonia 10
KZ - Kazakistan 10
SK - Slovacchia (Repubblica Slovacca) 10
AU - Australia 7
CR - Costa Rica 7
DZ - Algeria 7
KG - Kirghizistan 7
LT - Lituania 7
SY - Repubblica araba siriana 7
DO - Repubblica Dominicana 6
GR - Grecia 6
HR - Croazia 6
NI - Nicaragua 6
OM - Oman 6
UY - Uruguay 6
AL - Albania 5
PS - Palestinian Territory 5
TT - Trinidad e Tobago 5
AO - Angola 4
BA - Bosnia-Erzegovina 4
ET - Etiopia 4
GT - Guatemala 4
LV - Lettonia 4
PA - Panama 4
AM - Armenia 3
BH - Bahrain 3
GE - Georgia 3
HN - Honduras 3
LB - Libano 3
Totale 67.034
Città #
Ashburn 6.051
Southend 3.654
Seattle 3.004
Singapore 2.049
San Jose 1.388
Beijing 1.301
Chandler 1.259
Fairfield 1.117
Turin 1.003
Princeton 919
Jacksonville 897
Ho Chi Minh City 726
Hanoi 693
Council Bluffs 669
Ann Arbor 629
Woodbridge 574
Berlin 558
Dublin 531
Santa Clara 515
Izmir 513
San Ramon 491
Cambridge 474
Wilmington 461
Torino 459
Houston 455
Boardman 420
Hong Kong 414
Bern 409
Shanghai 404
Zhengzhou 404
Chicago 380
Milan 377
Helsinki 313
San Donato Milanese 274
Lauterbourg 259
Seoul 255
Los Angeles 244
Baltimore 234
Pennsylvania Furnace 220
Zaporozhye 220
Overberg 207
Dallas 194
Rome 190
San Mauro Torinese 176
Bologna 156
Vienna 155
Hefei 152
Da Nang 143
Saint Petersburg 141
Putian 139
Haiphong 132
Brussels 120
Mountain View 112
Redwood City 107
New York 105
Monopoli 104
Abu Dhabi 96
Moscow 96
Buffalo 88
São Paulo 87
Padua 79
Guangzhou 78
Gif-sur-yvette 77
Hangzhou 66
Paris 63
Munich 60
Bremen 59
Toronto 59
Frankfurt am Main 58
Malatya 57
San Diego 57
Genoa 56
Tokyo 56
Columbus 55
Atlanta 53
Orem 53
Washington 53
Norwalk 51
Porto Alegre 51
The Dalles 51
Modena 50
London 47
Amsterdam 46
Pisa 46
Changsha 45
Palermo 45
North Bergen 44
Piscataway 43
Bangkok 40
Melun 39
Yubileyny 38
Can Tho 37
Shenzhen 36
Montreal 35
Ankara 34
Genova 34
Strasbourg 34
Chennai 33
Biên Hòa 32
Hải Dương 32
Totale 39.899
Nome #
A tribute to Bruno Montagnini, Professor of Nuclear Reactor Physics, University of Pisa 784
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 692
Study of a low-power, fast-neutron-based ADS 459
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 445
PROPOSAL FOR THE UTILIZATION OF HONEY BEE AS AN EFFICIENT INDICATOR OF RADIACTIVE CONTAMINATION 438
A method for on-line reactivity monitoring in nuclear reactors 420
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 418
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 414
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 406
A method for the continuous monitoring of reactivity in subcritical source-driven systems 403
Assessment of an on-line reactivity monitoring technique 400
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 391
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 389
Assessment of the performance of the spectral element method applied to neutron transport problems 380
Alternative definitions of kinetic parameters for accelerator driven systems 373
Neutronic Evaluations for the EVOL Molten Salt Reactor 368
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 366
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 363
Integral parameters in source-driven systems 360
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 359
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 353
Integral neutron transport and new computational methods: a review 346
Reflector effects on the kinetic response in subcritical systems 343
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 343
Implementation of the quasi-static method for neutron transport 342
SP2 – Asymptotic P1 Equivalence 333
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 332
Alternative factorization methods for reactor kinetics 331
On the relation between spherical harmonics and simplified spherical harmonics methods 331
Evaluation of Ray Effects in Linear Transport Problems 330
Evaluation of ray effects in linear transport problems 328
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 326
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 322
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 320
Development of dynamic models for neutron transport calculations 317
Kinetics of a Point Reactor in the Presence of Reactivity Oscillations 316
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 311
Random effects on reactivity in molten salt reactors 311
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 307
The adjoint neutron transport equation and the statistical approach for its solution 306
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 306
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 304
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 302
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 301
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 301
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 300
A method for reactivity monitoring in subcritical source-driven systems 299
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 297
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 296
Coupled dynamics in the physics of molten salt reactors 296
Advanced Computational Models for Accelerator-Driven Systems 295
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 291
On the spectrum of the multigroup diffusion equations 290
An Approximate Method to Study the One-Velocity Neutron Integral Transport Equation 289
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 289
Assessment of a new method for reactivity measurement 288
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 287
Computational Methods for Multidimensional Neutron Diffusion Problems 287
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 286
From transport to diffusion through a space asymptotic approach 284
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 282
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 282
Some dynamic A-n, S-2n analytic calculations 282
XXI International Conference on Transport Theory 281
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 278
Application of a Numerical Laplace Transform Inversion Technique to a Problem in Reactor Dynamics 275
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 274
Alternative Forms of the Time-Dependent Neutron Transport Equation 274
Some Features of Spatial Neutron Kinetics for Multiplying Systems 273
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 273
Development of dynamic models for neutron transport calculations 273
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 272
Analytical approach to the neutron kinetics of the non-homogeneous reactor 267
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 267
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 267
Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems 267
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 265
SPECIAL ISSUE: IN HONOUR OF PROFESSOR BRUNO MONTAGNINI 265
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 265
Random Effects of Fissile Lumps in Molten Salt Reactors 263
Basic Reactor Physics Problems in Fluid-Fuel Recirculated Reactors 262
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 261
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 261
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 258
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 257
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 256
the An method and the Spherical harmonics approximation in neutron transport theory 255
Analysis of the Evolution of Perturbations in a Magnetized Collisionless Plasma with an Integral-Equation Technique 254
An alternative formulation of the monokinetic transport equation 253
Solution of 3D multigroup, linearly anisotropic scattering, criticality problems by the AN boundary-element response-matrix method 253
Three-Dimensional Neutron Analysis of Accelerator-Driven Systems 253
On the importance of effective convergence velocity of synthetic acceleration methods in neutron transport 253
Angular Finite Element Techniques in Neutron Transport 253
Variable grid finite difference methods for study of longitudinally varying planar waveguides 252
The time-dependent P1 model for the neutronics of multiplying systems: a review 252
The quasi-static method revisited 251
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 250
An Approximate method to study the one-velocity neutron Integral transport equation 248
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 247
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems” 246
Totale 31.584
Categoria #
all - tutte 192.710
article - articoli 90.590
book - libri 0
conference - conferenze 95.918
curatela - curatele 2.362
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.910
Totale 384.490


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202188 0 0 0 0 0 0 0 0 0 0 0 88
2021/20222.436 185 203 58 94 93 132 84 103 78 135 447 824
2022/20234.601 580 845 144 408 426 625 294 242 346 40 181 470
2023/20241.570 75 306 68 62 116 113 44 64 89 106 123 404
2024/20256.155 158 986 514 613 398 433 319 390 808 410 523 603
2025/202614.261 835 785 916 1.430 981 844 2.158 985 3.081 1.487 266 493
Totale 67.331