DULLA, SANDRA
 Distribuzione geografica
Continente #
EU - Europa 15.296
NA - Nord America 15.235
AS - Asia 3.742
SA - Sud America 237
AF - Africa 116
Continente sconosciuto - Info sul continente non disponibili 5
OC - Oceania 2
Totale 34.633
Nazione #
US - Stati Uniti d'America 15.077
IT - Italia 4.610
DE - Germania 2.643
GB - Regno Unito 2.460
FR - Francia 1.946
CN - Cina 1.786
UA - Ucraina 968
SG - Singapore 668
RU - Federazione Russa 519
TR - Turchia 442
IE - Irlanda 390
KR - Corea 349
CH - Svizzera 296
SE - Svezia 287
NL - Olanda 272
BE - Belgio 224
FI - Finlandia 217
BR - Brasile 199
CA - Canada 142
AT - Austria 114
JP - Giappone 89
AE - Emirati Arabi Uniti 68
HK - Hong Kong 68
IN - India 68
IR - Iran 49
ID - Indonesia 45
CI - Costa d'Avorio 44
ES - Italia 44
EU - Europa 36
AP - ???statistics.table.value.countryCode.AP??? 35
PK - Pakistan 34
RO - Romania 33
CZ - Repubblica Ceca 29
IL - Israele 21
BG - Bulgaria 20
SN - Senegal 20
EG - Egitto 19
VN - Vietnam 18
MY - Malesia 17
PT - Portogallo 16
SA - Arabia Saudita 16
AR - Argentina 15
NG - Nigeria 15
NO - Norvegia 15
CL - Cile 14
MX - Messico 14
BY - Bielorussia 12
LU - Lussemburgo 11
DK - Danimarca 10
SI - Slovenia 10
HU - Ungheria 9
SK - Slovacchia (Repubblica Slovacca) 9
IQ - Iraq 8
TW - Taiwan 8
CO - Colombia 6
HR - Croazia 6
JO - Giordania 6
PL - Polonia 6
EE - Estonia 5
PH - Filippine 5
TH - Thailandia 5
GR - Grecia 4
KZ - Kazakistan 3
TG - Togo 3
ZA - Sudafrica 3
ZW - Zimbabwe 3
AU - Australia 2
BD - Bangladesh 2
CM - Camerun 2
GT - Guatemala 2
KE - Kenya 2
MN - Mongolia 2
A2 - ???statistics.table.value.countryCode.A2??? 1
CY - Cipro 1
DZ - Algeria 1
EC - Ecuador 1
GH - Ghana 1
KG - Kirghizistan 1
LK - Sri Lanka 1
LT - Lituania 1
MA - Marocco 1
MO - Macao, regione amministrativa speciale della Cina 1
NP - Nepal 1
PE - Perù 1
QA - Qatar 1
SC - Seychelles 1
SY - Repubblica araba siriana 1
TN - Tunisia 1
UZ - Uzbekistan 1
VE - Venezuela 1
Totale 34.633
Città #
Ashburn 3.543
Southend 2.193
Seattle 1.793
Chandler 980
Turin 963
Fairfield 663
Beijing 636
Princeton 615
Council Bluffs 552
Jacksonville 503
Singapore 499
Ann Arbor 457
Santa Clara 439
Torino 422
San Ramon 374
Dublin 368
Berlin 364
Woodbridge 357
Houston 312
Boardman 308
Izmir 300
Cambridge 283
Wilmington 281
Shanghai 268
Zhengzhou 249
Milan 242
Bern 236
San Donato Milanese 179
Brussels 173
Chicago 173
Helsinki 163
San Mauro Torinese 150
Baltimore 129
Zaporozhye 124
Pennsylvania Furnace 117
Vienna 116
Rome 110
Overberg 104
Bologna 98
Saint Petersburg 96
Redwood City 77
Mountain View 69
Hefei 66
Monopoli 66
Abu Dhabi 61
Bremen 54
Padua 54
Piscataway 54
Istanbul 53
Paris 51
Gif-sur-yvette 50
Guangzhou 50
Hangzhou 50
New York 47
Abidjan 44
Toronto 43
Malatya 42
Redmond 41
Jakarta 40
Lappeenranta 37
Moscow 37
Yubileyny 37
Atlanta 36
Seoul 36
San Diego 35
Washington 34
Falls Church 33
Porto Alegre 33
Genova 31
Genoa 30
Harbin 28
Islamabad 28
Shenzhen 28
Amsterdam 27
London 27
Menlo Park 27
Norwalk 27
Palermo 26
Ankara 24
Caselle Torinese 23
Bottanuco 22
Frankfurt 22
Melun 22
Modena 22
Podenzano 22
Frankfurt Am Main 21
Karlsruhe 21
Nanjing 21
Andover 20
Putian 20
Borgosesia 19
Frankfurt am Main 19
Montréal 19
San Antonio 19
Aix-en-provence 18
Munich 18
Sofia 18
Xian 18
Grottaferrata 17
Kunming 17
Totale 21.983
Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 568
Study of a low-power, fast-neutron-based ADS 389
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 363
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 347
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 339
A method for on-line reactivity monitoring in nuclear reactors 336
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 324
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 316
Assessment of the performance of the spectral element method applied to neutron transport problems 311
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 308
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 303
PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT 303
Alternative definitions of kinetic parameters for accelerator driven systems 301
A method for the continuous monitoring of reactivity in subcritical source-driven systems 299
Assessment of an on-line reactivity monitoring technique 298
Implementation of the quasi-static method for neutron transport 296
Integral parameters in source-driven systems 296
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 293
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 286
Alternative factorization methods for reactor kinetics 280
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 277
Integral neutron transport and new computational methods: a review 276
Neutronic Evaluations for the EVOL Molten Salt Reactor 275
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 271
Evaluation of ray effects in linear transport problems 264
Evaluation of Ray Effects in Linear Transport Problems 258
Development of dynamic models for neutron transport calculations 253
Random effects on reactivity in molten salt reactors 253
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 252
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 245
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 243
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 243
Alternative Forms of the Time-Dependent Neutron Transport Equation 242
On the spectrum of the multigroup diffusion equations 239
Coupled dynamics in the physics of molten salt reactors 238
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 237
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 236
Computational Methods for Multidimensional Neutron Diffusion Problems 235
Performance of Non-Conventional Factorization Approaches for Neutron Kinetics 234
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 233
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 231
Development of dynamic models for neutron transport calculations 230
The adjoint neutron transport equation and the statistical approach for its solution 230
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 230
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 230
Reflector effects on the kinetic response in subcritical systems 229
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 229
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 228
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 228
From transport to diffusion through a space asymptotic approach 227
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 226
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 226
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 225
Assessment of a new method for reactivity measurement 225
Dynamics of fluid fuel reactors in the presence of periodic perturbations 225
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 224
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 223
Analytical approach to the neutron kinetics of the non-homogeneous reactor 222
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 220
Consistent multipoint kinetics for source-driven systems 218
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 215
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 212
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 210
XXI International Conference on Transport Theory 210
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 210
Numerical aspects in the study of neutron propagation 209
Some Features of Spatial Neutron Kinetics for Multiplying Systems 206
Random Effects of Fissile Lumps in Molten Salt Reactors 206
A cellular automaton model for offshore evacuation risk assessment 204
A method for reactivity monitoring in subcritical source-driven systems 204
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 203
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 202
The quasi-static method revisited 200
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 200
General expression of the calibration curve for the CR-39 radon track detectors 200
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 200
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 199
The time-dependent P1 model for the neutronics of multiplying systems: a review 199
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 199
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 198
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 197
The spectral element approach for the solution of neutron transport problems 197
Neutron kinetics of fluid-fuel systems by the quasi-static method 196
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 194
Multiphysics approach to the analysis of molten salt reactors 189
Nuclear engineering master thesis projects at Politecnico di Torino 185
The migration mode method in neutron transport theory 185
Transport Effects for Source-Oscillated Problems in Subcritical Systems 184
On Some Features of Spatial Neutron Kinetics for Multiplying Systems 183
Transport Effects for Source-Oscillated Problems in Subcritical Systems 178
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 177
Reactivity oscillations in molten salt reactors 176
Analysis of the Role of Fluid-Dynamic Phenomena in the Neutronics of Molten-Salt Systems 175
The Neutronics of a Burning-Breeding Nuclear System 173
On the exact solution for the multi-group kinetic neutron diffusion equation in a rectangle 171
A response matrix formulation of multidimensional transport problems 170
Interpretation of local flux measurements for reactivity prediction 170
Multipoint method for the neutron kinetics of decoupled systems 170
Methods in integral neutron transport 169
A quasi-static transport module using the DRAGON code 168
Totale 23.779
Categoria #
all - tutte 99.131
article - articoli 42.279
book - libri 0
conference - conferenze 53.719
curatela - curatele 639
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 1.745
Totale 197.513


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2019/20201.639 0 0 0 0 0 291 156 393 342 293 101 63
2020/20212.326 330 308 94 308 89 221 123 197 117 243 228 68
2021/20221.967 151 127 64 108 70 100 89 79 91 117 367 604
2022/20233.596 386 643 124 362 332 448 232 219 282 51 159 358
2023/20241.787 63 321 82 106 127 153 89 91 116 110 144 385
2024/20253.192 163 885 456 702 500 486 0 0 0 0 0 0
Totale 34.970