PORTO @ Archivio Istituzionale della Ricerca

RAVETTO, PIERO
 Distribuzione geografica
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Continente #
EU - Europa 22.444
NA - Nord America 22.219
AS - Asia 5.696
SA - Sud America 430
AF - Africa 81
OC - Oceania 5
Continente sconosciuto - Info sul continente non disponibili 4
Totale 50.879
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Nazione #
US - Stati Uniti d'America 22.027
IT - Italia 5.938
GB - Regno Unito 4.005
DE - Germania 3.760
FR - Francia 3.192
CN - Cina 2.672
UA - Ucraina 1.843
SG - Singapore 1.274
RU - Federazione Russa 804
TR - Turchia 653
IE - Irlanda 536
KR - Corea 475
SE - Svezia 469
CH - Svizzera 459
NL - Olanda 406
BR - Brasile 361
FI - Finlandia 294
BE - Belgio 182
AT - Austria 162
CA - Canada 139
JP - Giappone 121
AE - Emirati Arabi Uniti 114
IN - India 88
IR - Iran 61
AP - ???statistics.table.value.countryCode.AP??? 55
HK - Hong Kong 53
MX - Messico 47
EU - Europa 41
ES - Italia 38
PK - Pakistan 37
RO - Romania 36
IL - Israele 33
MY - Malesia 32
AR - Argentina 31
VN - Vietnam 28
CZ - Repubblica Ceca 26
ID - Indonesia 25
NG - Nigeria 18
SA - Arabia Saudita 18
SN - Senegal 18
PT - Portogallo 17
CL - Cile 16
NO - Norvegia 16
EG - Egitto 15
LU - Lussemburgo 15
BY - Bielorussia 13
CI - Costa d'Avorio 13
BG - Bulgaria 12
PL - Polonia 12
TW - Taiwan 12
DK - Danimarca 10
EE - Estonia 10
SI - Slovenia 10
SK - Slovacchia (Repubblica Slovacca) 9
CO - Colombia 8
HU - Ungheria 8
GR - Grecia 6
PH - Filippine 6
TH - Thailandia 6
AU - Australia 5
BD - Bangladesh 5
HR - Croazia 5
IQ - Iraq 5
KZ - Kazakistan 5
UZ - Uzbekistan 5
VE - Venezuela 5
JO - Giordania 4
ZA - Sudafrica 4
AZ - Azerbaigian 3
GT - Guatemala 3
LV - Lettonia 3
PE - Perù 3
ZW - Zimbabwe 3
CM - Camerun 2
EC - Ecuador 2
KG - Kirghizistan 2
LK - Sri Lanka 2
LT - Lituania 2
MA - Marocco 2
MN - Mongolia 2
NP - Nepal 2
PY - Paraguay 2
TN - Tunisia 2
A2 - ???statistics.table.value.countryCode.A2??? 1
AM - Armenia 1
BA - Bosnia-Erzegovina 1
BO - Bolivia 1
CR - Costa Rica 1
DZ - Algeria 1
GH - Ghana 1
GI - Gibilterra 1
JM - Giamaica 1
KE - Kenya 1
MD - Moldavia 1
MO - Macao, regione amministrativa speciale della Cina 1
NI - Nicaragua 1
SC - Seychelles 1
SY - Repubblica araba siriana 1
UY - Uruguay 1
Totale 50.879
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Città #
Ashburn 5.579
Southend 3.654
Seattle 3.000
Chandler 1.258
Fairfield 1.117
Beijing 1.076
Princeton 918
Turin 911
Jacksonville 894
Ann Arbor 629
Council Bluffs 610
Woodbridge 574
Singapore 566
Berlin 554
Dublin 525
Izmir 512
San Ramon 491
Cambridge 471
Wilmington 460
Torino 459
Houston 442
Santa Clara 423
Bern 409
Boardman 406
Zhengzhou 391
Shanghai 369
Chicago 368
Milan 309
San Donato Milanese 274
Helsinki 259
Baltimore 232
Pennsylvania Furnace 220
Zaporozhye 220
Overberg 207
San Mauro Torinese 176
Vienna 152
Rome 145
Saint Petersburg 141
Putian 139
Bologna 137
Brussels 120
Mountain View 112
Redwood City 107
Monopoli 104
Hefei 100
Abu Dhabi 94
Padua 78
Gif-sur-yvette 77
Hangzhou 63
Moscow 61
Bremen 59
Malatya 57
Paris 56
San Diego 56
Toronto 55
Washington 52
Norwalk 51
Guangzhou 50
Modena 50
New York 50
Atlanta 46
Pisa 45
Piscataway 43
Palermo 41
Melun 39
Porto Alegre 38
Yubileyny 38
Genoa 36
Genova 34
Strasbourg 34
London 32
Harbin 31
Karlsruhe 31
Seoul 31
Amsterdam 30
Andover 28
Islamabad 28
Istanbul 27
Shenzhen 27
Frankfurt 26
Frankfurt Am Main 26
Mexico 26
Ankara 25
Changsha 24
Frankfurt am Main 24
Hanoi 24
Caselle Torinese 23
Lappeenranta 23
Xian 23
Bottanuco 22
Falls Church 22
Jakarta 22
Ningbo 20
Podenzano 20
Redmond 20
Kunming 19
Nanjing 19
San Francisco 19
Aix-en-provence 18
Minerbio 18
Totale 32.251
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Nome #
A tribute to Bruno Montagnini, Professor of Nuclear Reactor Physics, University of Pisa 690
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 577
PROPOSAL FOR THE UTILIZATION OF HONEY BEE AS AN EFFICIENT INDICATOR OF RADIACTIVE CONTAMINATION 399
Study of a low-power, fast-neutron-based ADS 394
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 369
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 351
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 346
A method for on-line reactivity monitoring in nuclear reactors 344
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 331
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 324
Assessment of the performance of the spectral element method applied to neutron transport problems 315
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 315
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 311
Alternative definitions of kinetic parameters for accelerator driven systems 311
A method for the continuous monitoring of reactivity in subcritical source-driven systems 308
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 304
Assessment of an on-line reactivity monitoring technique 303
Integral parameters in source-driven systems 301
Implementation of the quasi-static method for neutron transport 300
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 290
Alternative factorization methods for reactor kinetics 283
Neutronic Evaluations for the EVOL Molten Salt Reactor 282
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 281
Integral neutron transport and new computational methods: a review 281
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 275
Evaluation of ray effects in linear transport problems 269
SP2 – Asymptotic P1 Equivalence 265
Development of dynamic models for neutron transport calculations 264
Evaluation of Ray Effects in Linear Transport Problems 261
Random effects on reactivity in molten salt reactors 258
Kinetics of a Point Reactor in the Presence of Reactivity Oscillations 255
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 255
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 251
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 250
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 248
On the spectrum of the multigroup diffusion equations 247
On the relation between spherical harmonics and simplified spherical harmonics methods 246
An Approximate Method to Study the One-Velocity Neutron Integral Transport Equation 245
Alternative Forms of the Time-Dependent Neutron Transport Equation 245
Coupled dynamics in the physics of molten salt reactors 245
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 244
Reflector effects on the kinetic response in subcritical systems 242
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 242
Computational Methods for Multidimensional Neutron Diffusion Problems 241
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 240
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 236
The adjoint neutron transport equation and the statistical approach for its solution 236
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 236
Development of dynamic models for neutron transport calculations 235
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 234
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 234
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 233
Assessment of a new method for reactivity measurement 233
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 233
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 231
Application of a Numerical Laplace Transform Inversion Technique to a Problem in Reactor Dynamics 231
Advanced Computational Models for Accelerator-Driven Systems 230
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 230
Some dynamic A-n, S-2n analytic calculations 230
From transport to diffusion through a space asymptotic approach 229
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 228
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 227
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 227
Analytical approach to the neutron kinetics of the non-homogeneous reactor 225
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 224
Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems 222
the An method and the Spherical harmonics approximation in neutron transport theory 221
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 218
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 217
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 217
An alternative formulation of the monokinetic transport equation 216
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 216
XXI International Conference on Transport Theory 213
A method for reactivity monitoring in subcritical source-driven systems 213
Numerical aspects in the study of neutron propagation 211
Analysis of the Evolution of Perturbations in a Magnetized Collisionless Plasma with an Integral-Equation Technique 211
Angular Finite Element Techniques in Neutron Transport 211
Basic Reactor Physics Problems in Fluid-Fuel Recirculated Reactors 210
Random Effects of Fissile Lumps in Molten Salt Reactors 210
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 210
SPECIAL ISSUE: IN HONOUR OF PROFESSOR BRUNO MONTAGNINI 209
Solution of 3D multigroup, linearly anisotropic scattering, criticality problems by the AN boundary-element response-matrix method 209
Some Features of Spatial Neutron Kinetics for Multiplying Systems 208
Reactivity Oscillations in a Point Reactor 208
Three-Dimensional Neutron Analysis of Accelerator-Driven Systems 206
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 205
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 205
Variable grid finite difference methods for study of longitudinally varying planar waveguides 204
An Approximate method to study the one-velocity neutron Integral transport equation 204
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 204
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 204
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 203
The quasi-static method revisited 202
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 202
New Approach to the problem of the propagation of electrostatic perturbations in Vlasov plasmas 202
The time-dependent P1 model for the neutronics of multiplying systems: a review 201
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 200
A Synthesis Method in the Study of Linear Forced Oscillations in a Collisionless Plasma 200
Application of the Multipoint Method to the Kinetics of Accelerator-Driven Systems 200
Neutron kinetics of fluid-fuel systems by the quasi-static method 199
Totale 25.511
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Categoria #
all - tutte 148.707
article - articoli 69.918
book - libri 0
conference - conferenze 74.121
curatela - curatele 1.867
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.298
Totale 296.911
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20201.182 0 0 0 0 0 0 0 0 531 413 140 98
2020/20213.406 533 495 137 453 102 364 149 297 165 333 290 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
2023/20241.575 75 306 68 62 116 117 44 64 89 106 123 405
2024/20254.195 158 988 514 613 400 433 319 391 379 0 0 0
Totale 51.115