DULLA, SANDRA
 Distribuzione geografica
Continente #
NA - Nord America 20.898
EU - Europa 18.280
AS - Asia 12.525
SA - Sud America 1.314
Continente sconosciuto - Info sul continente non disponibili 412
AF - Africa 222
OC - Oceania 11
Totale 53.662
Nazione #
US - Stati Uniti d'America 20.518
IT - Italia 5.675
SG - Singapore 3.369
CN - Cina 3.047
DE - Germania 2.840
VN - Vietnam 2.823
GB - Regno Unito 2.559
FR - Francia 2.250
RU - Federazione Russa 1.395
BR - Brasile 1.073
UA - Ucraina 990
KR - Corea 806
HK - Hong Kong 509
TR - Turchia 485
IE - Irlanda 396
IN - India 352
NL - Olanda 338
CH - Svizzera 308
SE - Svezia 307
FI - Finlandia 301
CA - Canada 240
BE - Belgio 235
BD - Bangladesh 205
JP - Giappone 187
AT - Austria 166
ES - Italia 120
AR - Argentina 82
PH - Filippine 78
TH - Thailandia 78
AE - Emirati Arabi Uniti 77
IQ - Iraq 75
TW - Taiwan 72
ID - Indonesia 69
PK - Pakistan 57
IR - Iran 51
MX - Messico 51
CI - Costa d'Avorio 46
IL - Israele 42
EC - Ecuador 40
RO - Romania 38
EU - Europa 36
AP - ???statistics.table.value.countryCode.AP??? 35
CO - Colombia 34
ZA - Sudafrica 33
CL - Cile 32
EG - Egitto 32
CZ - Repubblica Ceca 31
SA - Arabia Saudita 31
MY - Malesia 28
PL - Polonia 28
BG - Bulgaria 27
SN - Senegal 27
PT - Portogallo 24
UZ - Uzbekistan 22
JO - Giordania 21
VE - Venezuela 20
NG - Nigeria 19
DK - Danimarca 18
CR - Costa Rica 17
JM - Giamaica 17
BY - Bielorussia 16
NO - Norvegia 16
PY - Paraguay 16
AZ - Azerbaigian 14
NP - Nepal 14
SI - Slovenia 14
LU - Lussemburgo 13
MA - Marocco 13
HU - Ungheria 12
KE - Kenya 12
PE - Perù 12
AU - Australia 11
SK - Slovacchia (Repubblica Slovacca) 11
TN - Tunisia 10
HR - Croazia 9
LT - Lituania 9
GT - Guatemala 8
SY - Repubblica araba siriana 8
TT - Trinidad e Tobago 8
DO - Repubblica Dominicana 7
DZ - Algeria 7
GR - Grecia 7
NI - Nicaragua 7
OM - Oman 7
HN - Honduras 6
KG - Kirghizistan 6
KZ - Kazakistan 6
AL - Albania 5
EE - Estonia 5
PA - Panama 5
SV - El Salvador 5
MN - Mongolia 4
PR - Porto Rico 4
RS - Serbia 4
UY - Uruguay 4
AM - Armenia 3
BH - Bahrain 3
ET - Etiopia 3
GE - Georgia 3
PS - Palestinian Territory 3
Totale 53.212
Città #
Ashburn 4.164
Southend 2.193
Singapore 1.881
Seattle 1.802
Turin 1.216
San Jose 1.157
Chandler 980
Beijing 887
Council Bluffs 822
Ho Chi Minh City 704
Fairfield 663
Hanoi 661
Princeton 615
Santa Clara 538
Jacksonville 505
Ann Arbor 457
Milan 426
Torino 422
Dublin 374
San Ramon 374
Berlin 367
Hong Kong 361
Woodbridge 358
Boardman 344
Dallas 340
Houston 327
Seoul 317
Izmir 301
Shanghai 301
Cambridge 289
Wilmington 282
Zhengzhou 260
Los Angeles 241
Bern 236
Rome 232
Helsinki 197
Lauterbourg 193
Chicago 190
San Donato Milanese 179
Brussels 176
Hefei 170
San Mauro Torinese 150
Da Nang 140
Baltimore 132
Vienna 131
Bologna 128
New York 126
Zaporozhye 124
Pennsylvania Furnace 117
Haiphong 115
Moscow 111
Overberg 104
Saint Petersburg 96
Buffalo 88
Munich 81
Redwood City 77
Frankfurt am Main 76
São Paulo 75
Tokyo 71
Mountain View 69
Columbus 68
Guangzhou 68
Monopoli 66
The Dalles 64
Abu Dhabi 62
Paris 61
Istanbul 59
Padua 57
Toronto 57
Lappeenranta 55
Piscataway 55
Bremen 54
Hangzhou 53
Atlanta 51
Genoa 50
Gif-sur-yvette 50
Orem 50
Porto Alegre 48
Abidjan 46
Jakarta 46
Amsterdam 44
Can Tho 44
North Bergen 43
London 42
Malatya 42
Montreal 41
Redmond 41
Washington 40
Ankara 39
Shenzhen 37
Yubileyny 37
Bangkok 35
Nuremberg 35
San Diego 35
Falls Church 33
Barcelona 32
Palermo 32
Phoenix 32
Genova 31
Changsha 29
Totale 30.377
Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 702
Divertor Tokamak Test facility project: status of design and implementation 611
PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT 467
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 447
A method for on-line reactivity monitoring in nuclear reactors 422
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 421
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 417
A method for the continuous monitoring of reactivity in subcritical source-driven systems 408
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 407
Assessment of an on-line reactivity monitoring technique 402
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 397
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 394
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 392
Assessment of the performance of the spectral element method applied to neutron transport problems 384
Alternative definitions of kinetic parameters for accelerator driven systems 375
Neutronic Evaluations for the EVOL Molten Salt Reactor 370
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 364
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 364
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 362
Integral parameters in source-driven systems 362
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 356
Integral neutron transport and new computational methods: a review 348
Reflector effects on the kinetic response in subcritical systems 346
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 344
Implementation of the quasi-static method for neutron transport 342
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 335
Evaluation of Ray Effects in Linear Transport Problems 333
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 332
Alternative factorization methods for reactor kinetics 332
Evaluation of ray effects in linear transport problems 329
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 327
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 325
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 325
Development of dynamic models for neutron transport calculations 320
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 312
Random effects on reactivity in molten salt reactors 311
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 309
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 309
The adjoint neutron transport equation and the statistical approach for its solution 308
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 308
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 307
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 306
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 306
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 306
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 305
A method for reactivity monitoring in subcritical source-driven systems 302
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 299
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 297
Coupled dynamics in the physics of molten salt reactors 297
On the spectrum of the multigroup diffusion equations 293
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 293
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 292
Performance of Non-Conventional Factorization Approaches for Neutron Kinetics 290
Dynamics of fluid fuel reactors in the presence of periodic perturbations 290
Computational Methods for Multidimensional Neutron Diffusion Problems 289
Assessment of a new method for reactivity measurement 288
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 287
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 287
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 287
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 287
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 286
From transport to diffusion through a space asymptotic approach 285
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 284
XXI International Conference on Transport Theory 282
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 281
Development of dynamic models for neutron transport calculations 276
Alternative Forms of the Time-Dependent Neutron Transport Equation 276
Some Features of Spatial Neutron Kinetics for Multiplying Systems 275
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 275
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 275
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 274
Analytical approach to the neutron kinetics of the non-homogeneous reactor 269
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 268
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 268
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 268
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 267
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 265
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 263
Random Effects of Fissile Lumps in Molten Salt Reactors 263
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 263
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 261
Consistent multipoint kinetics for source-driven systems 261
General expression of the calibration curve for the CR-39 radon track detectors 260
Nuclear data uncertainty quantification in the ARC fusion reactor 258
Alternative Weighting Functions for Group Collapsing of Nuclear Data in Lead Fast Reactors Time-dependent Analyses 258
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 258
A cellular automaton model for offshore evacuation risk assessment 257
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 256
The time-dependent P1 model for the neutronics of multiplying systems: a review 253
The quasi-static method revisited 252
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 252
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems” 248
A methodology for the identification of the postulated initiating events of the Molten Salt Fast Reactor 248
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 246
The spectral element approach for the solution of neutron transport problems 244
The migration mode method in neutron transport theory 244
A response matrix formulation of multidimensional transport problems 242
Neutron kinetics of fluid-fuel systems by the quasi-static method 242
Nuclear engineering master thesis projects at Politecnico di Torino 241
Totale 31.630
Categoria #
all - tutte 149.609
article - articoli 66.267
book - libri 0
conference - conferenze 78.619
curatela - curatele 855
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.347
Totale 297.697


Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/20221.816 0 127 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
2023/20241.782 63 321 82 106 127 149 89 91 116 110 144 384
2024/20256.563 163 883 456 702 498 490 439 451 774 455 636 616
2025/202614.560 899 718 986 1.173 1.086 833 2.010 1.124 3.107 1.478 356 790
2026/2027766 448 318 0 0 0 0 0 0 0 0 0 0
Totale 53.662