PORTO @ Archivio Istituzionale della Ricerca

DULLA, SANDRA
 Distribuzione geografica
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Continente #
NA - Nord America 19.846
EU - Europa 17.700
AS - Asia 12.258
SA - Sud America 1.279
AF - Africa 221
OC - Oceania 11
Continente sconosciuto - Info sul continente non disponibili 6
Totale 51.321
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Nazione #
US - Stati Uniti d'America 19.569
IT - Italia 5.170
SG - Singapore 3.296
CN - Cina 3.027
DE - Germania 2.834
VN - Vietnam 2.820
GB - Regno Unito 2.557
FR - Francia 2.240
RU - Federazione Russa 1.394
BR - Brasile 1.057
UA - Ucraina 989
KR - Corea 802
HK - Hong Kong 506
TR - Turchia 481
IE - Irlanda 396
IN - India 351
NL - Olanda 324
CH - Svizzera 302
SE - Svezia 301
FI - Finlandia 299
BE - Belgio 234
CA - Canada 194
JP - Giappone 181
AT - Austria 166
ES - Italia 101
AR - Argentina 78
TH - Thailandia 78
PH - Filippine 77
AE - Emirati Arabi Uniti 76
IQ - Iraq 75
TW - Taiwan 72
ID - Indonesia 68
PK - Pakistan 57
BD - Bangladesh 56
IR - Iran 50
MX - Messico 47
CI - Costa d'Avorio 46
IL - Israele 42
RO - Romania 38
EU - Europa 36
AP - ???statistics.table.value.countryCode.AP??? 35
EC - Ecuador 35
EG - Egitto 32
ZA - Sudafrica 32
CZ - Repubblica Ceca 31
SA - Arabia Saudita 31
CO - Colombia 30
CL - Cile 29
MY - Malesia 28
PL - Polonia 27
SN - Senegal 27
BG - Bulgaria 25
PT - Portogallo 24
UZ - Uzbekistan 22
JO - Giordania 21
NG - Nigeria 19
VE - Venezuela 19
DK - Danimarca 18
BY - Bielorussia 16
NO - Norvegia 16
PY - Paraguay 15
AZ - Azerbaigian 14
NP - Nepal 14
SI - Slovenia 14
MA - Marocco 13
HU - Ungheria 12
KE - Kenya 12
LU - Lussemburgo 12
AU - Australia 11
PE - Perù 11
SK - Slovacchia (Repubblica Slovacca) 11
TN - Tunisia 10
HR - Croazia 9
LT - Lituania 8
SY - Repubblica araba siriana 8
DO - Repubblica Dominicana 7
DZ - Algeria 7
GR - Grecia 7
OM - Oman 7
CR - Costa Rica 6
JM - Giamaica 6
KG - Kirghizistan 6
KZ - Kazakistan 6
EE - Estonia 5
AL - Albania 4
MN - Mongolia 4
PA - Panama 4
RS - Serbia 4
UY - Uruguay 4
AM - Armenia 3
BH - Bahrain 3
ET - Etiopia 3
GE - Georgia 3
GT - Guatemala 3
PS - Palestinian Territory 3
TG - Togo 3
TT - Trinidad e Tobago 3
ZW - Zimbabwe 3
AO - Angola 2
BA - Bosnia-Erzegovina 2
Totale 51.286
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Città #
Ashburn 4.070
Southend 2.193
Singapore 1.873
Seattle 1.800
Turin 1.177
San Jose 984
Chandler 980
Beijing 882
Ho Chi Minh City 704
Fairfield 663
Hanoi 660
Council Bluffs 654
Princeton 615
Santa Clara 506
Jacksonville 504
Ann Arbor 457
Torino 422
Dublin 374
San Ramon 374
Berlin 367
Hong Kong 359
Woodbridge 357
Dallas 326
Houston 324
Seoul 316
Boardman 309
Milan 306
Izmir 301
Shanghai 301
Cambridge 289
Wilmington 281
Zhengzhou 260
Bern 236
Los Angeles 216
Helsinki 196
Lauterbourg 193
Chicago 186
San Donato Milanese 179
Brussels 175
Hefei 169
San Mauro Torinese 150
Rome 144
Da Nang 139
Baltimore 131
Vienna 131
Zaporozhye 124
Pennsylvania Furnace 117
Bologna 116
Haiphong 115
Moscow 111
Overberg 104
Saint Petersburg 96
New York 92
Munich 81
Buffalo 77
Redwood City 77
Frankfurt am Main 74
São Paulo 71
Mountain View 69
Guangzhou 68
Tokyo 68
Columbus 66
Monopoli 66
Abu Dhabi 62
Istanbul 59
The Dalles 58
Paris 57
Lappeenranta 55
Bremen 54
Padua 54
Piscataway 54
Toronto 54
Hangzhou 53
Gif-sur-yvette 50
Atlanta 49
Genoa 49
Orem 48
Porto Alegre 48
Abidjan 46
Jakarta 46
Amsterdam 44
Can Tho 44
North Bergen 43
London 42
Malatya 42
Redmond 41
Shenzhen 37
Yubileyny 37
Ankara 36
Bangkok 35
Nuremberg 35
San Diego 35
Washington 34
Falls Church 33
Montreal 33
Genova 31
Palermo 30
Changsha 29
Chennai 29
Phoenix 29
Totale 29.440
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 688
Divertor Tokamak Test facility project: status of design and implementation 504
Study of a low-power, fast-neutron-based ADS 456
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 440
PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT 429
A method for on-line reactivity monitoring in nuclear reactors 417
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 411
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 410
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 405
A method for the continuous monitoring of reactivity in subcritical source-driven systems 400
Assessment of an on-line reactivity monitoring technique 396
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 389
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 388
Assessment of the performance of the spectral element method applied to neutron transport problems 379
Alternative definitions of kinetic parameters for accelerator driven systems 373
Neutronic Evaluations for the EVOL Molten Salt Reactor 366
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 361
Integral parameters in source-driven systems 360
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 357
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 349
Integral neutron transport and new computational methods: a review 342
Implementation of the quasi-static method for neutron transport 341
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 339
Reflector effects on the kinetic response in subcritical systems 336
Alternative factorization methods for reactor kinetics 331
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 330
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 328
Evaluation of Ray Effects in Linear Transport Problems 327
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 325
Evaluation of ray effects in linear transport problems 322
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 321
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 319
Development of dynamic models for neutron transport calculations 316
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 310
Random effects on reactivity in molten salt reactors 310
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 306
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 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
The adjoint neutron transport equation and the statistical approach for its solution 304
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 302
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 300
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 300
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 299
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 298
Coupled dynamics in the physics of molten salt reactors 296
A method for reactivity monitoring in subcritical source-driven systems 296
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 295
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 294
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 293
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 290
On the spectrum of the multigroup diffusion equations 287
Assessment of a new method for reactivity measurement 287
Dynamics of fluid fuel reactors in the presence of periodic perturbations 287
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 287
Performance of Non-Conventional Factorization Approaches for Neutron Kinetics 285
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 284
Computational Methods for Multidimensional Neutron Diffusion Problems 284
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 283
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 282
From transport to diffusion through a space asymptotic approach 280
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 280
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 279
XXI International Conference on Transport Theory 277
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 276
Development of dynamic models for neutron transport calculations 273
Alternative Forms of the Time-Dependent Neutron Transport Equation 272
Some Features of Spatial Neutron Kinetics for Multiplying Systems 271
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 271
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 271
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 268
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 267
Analytical approach to the neutron kinetics of the non-homogeneous reactor 264
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 263
Random Effects of Fissile Lumps in Molten Salt Reactors 262
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 261
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 260
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 259
Consistent multipoint kinetics for source-driven systems 259
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 259
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 258
General expression of the calibration curve for the CR-39 radon track detectors 257
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 255
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 254
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 252
A cellular automaton model for offshore evacuation risk assessment 252
The time-dependent P1 model for the neutronics of multiplying systems: a review 250
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 249
The quasi-static method revisited 247
Nuclear data uncertainty quantification in the ARC fusion reactor 246
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 245
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems” 244
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 244
The spectral element approach for the solution of neutron transport problems 242
A methodology for the identification of the postulated initiating events of the Molten Salt Fast Reactor 241
The migration mode method in neutron transport theory 239
A response matrix formulation of multidimensional transport problems 237
Methods in integral neutron transport 237
Multiphysics approach to the analysis of molten salt reactors 237
Nuclear engineering master thesis projects at Politecnico di Torino 237
Totale 30.825
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Categoria #
all - tutte 138.417
article - articoli 61.029
book - libri 0
conference - conferenze 72.989
curatela - curatele 814
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.214
Totale 275.463
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/2021539 0 0 0 0 0 0 0 0 0 243 228 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
2023/20241.782 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
2025/202613.371 899 718 986 1.173 1.086 833 2.010 1.124 3.107 1.435 0 0
Totale 51.707