PORTO @ Archivio Istituzionale della Ricerca

DULLA, SANDRA
 Distribuzione geografica
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Continente #
NA - Nord America 17.864
EU - Europa 16.335
AS - Asia 7.866
SA - Sud America 1.140
AF - Africa 175
OC - Oceania 7
Continente sconosciuto - Info sul continente non disponibili 5
Totale 43.392
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Nazione #
US - Stati Uniti d'America 17.617
IT - Italia 5.024
CN - Cina 2.902
SG - Singapore 2.806
DE - Germania 2.781
GB - Regno Unito 2.505
FR - Francia 2.016
UA - Ucraina 981
BR - Brasile 974
RU - Federazione Russa 601
KR - Corea 597
TR - Turchia 471
IE - Irlanda 395
NL - Olanda 306
SE - Svezia 300
CH - Svizzera 299
FI - Finlandia 265
BE - Belgio 233
VN - Vietnam 227
HK - Hong Kong 187
CA - Canada 182
AT - Austria 162
JP - Giappone 127
IN - India 103
ES - Italia 97
AE - Emirati Arabi Uniti 72
AR - Argentina 62
ID - Indonesia 61
IR - Iran 50
PK - Pakistan 46
CI - Costa d'Avorio 45
MX - Messico 42
IL - Israele 41
EU - Europa 36
RO - Romania 36
AP - ???statistics.table.value.countryCode.AP??? 35
IQ - Iraq 35
BD - Bangladesh 31
CZ - Repubblica Ceca 30
PL - Polonia 27
EC - Ecuador 25
SN - Senegal 25
BG - Bulgaria 23
CO - Colombia 23
SA - Arabia Saudita 23
EG - Egitto 22
ZA - Sudafrica 22
CL - Cile 21
MY - Malesia 20
DK - Danimarca 18
PT - Portogallo 18
NG - Nigeria 17
UZ - Uzbekistan 17
NO - Norvegia 16
BY - Bielorussia 14
JO - Giordania 13
PY - Paraguay 13
SI - Slovenia 13
VE - Venezuela 13
LU - Lussemburgo 12
HU - Ungheria 11
MA - Marocco 10
SK - Slovacchia (Repubblica Slovacca) 10
TW - Taiwan 10
AZ - Azerbaigian 9
NP - Nepal 9
KE - Kenya 8
LT - Lituania 8
PH - Filippine 8
TH - Thailandia 8
AU - Australia 7
GR - Grecia 7
HR - Croazia 7
DZ - Algeria 6
PE - Perù 6
DO - Repubblica Dominicana 5
EE - Estonia 5
KG - Kirghizistan 5
JM - Giamaica 4
KZ - Kazakistan 4
MN - Mongolia 4
TN - Tunisia 4
AL - Albania 3
AM - Armenia 3
BH - Bahrain 3
GT - Guatemala 3
OM - Oman 3
TG - Togo 3
UY - Uruguay 3
ZW - Zimbabwe 3
BN - Brunei Darussalam 2
CM - Camerun 2
CR - Costa Rica 2
ET - Etiopia 2
NI - Nicaragua 2
PA - Panama 2
PS - Palestinian Territory 2
SC - Seychelles 2
SY - Repubblica araba siriana 2
TT - Trinidad e Tobago 2
Totale 43.374
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Città #
Ashburn 3.859
Southend 2.193
Seattle 1.798
Singapore 1.492
Turin 1.132
Chandler 980
Beijing 867
Fairfield 663
Council Bluffs 623
Princeton 615
Jacksonville 504
Santa Clara 486
Ann Arbor 457
Torino 422
San Ramon 374
Dublin 373
Berlin 365
Woodbridge 357
Houston 322
Dallas 317
Boardman 308
Izmir 301
Shanghai 299
Milan 296
Cambridge 286
Wilmington 281
Zhengzhou 260
Bern 236
Chicago 181
San Donato Milanese 179
Brussels 175
Seoul 171
Helsinki 165
Hefei 164
San Mauro Torinese 150
Rome 131
Baltimore 129
Vienna 127
Hong Kong 126
Zaporozhye 124
Pennsylvania Furnace 117
Bologna 108
Overberg 104
Saint Petersburg 96
Los Angeles 94
Munich 81
Redwood City 77
New York 76
Buffalo 73
Hanoi 70
Ho Chi Minh City 70
Mountain View 69
Guangzhou 67
Monopoli 66
Abu Dhabi 62
São Paulo 60
Istanbul 56
Bremen 54
Padua 54
Piscataway 53
Hangzhou 52
Lappeenranta 52
Paris 51
Gif-sur-yvette 50
Toronto 50
Atlanta 47
Frankfurt am Main 47
Moscow 47
Porto Alegre 46
Abidjan 45
Columbus 45
Tokyo 45
Jakarta 44
North Bergen 43
The Dalles 43
Malatya 42
Redmond 41
Yubileyny 37
London 35
San Diego 35
Shenzhen 35
Ankara 34
San Jose 34
Washington 34
Falls Church 33
Genoa 33
Amsterdam 32
Nuremberg 32
Genova 31
Montreal 29
Changsha 28
Harbin 28
Islamabad 28
Palermo 28
Phoenix 28
Menlo Park 27
Norwalk 27
Melun 26
Turku 25
Nanjing 24
Totale 25.288
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 644
Study of a low-power, fast-neutron-based ADS 428
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 405
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 391
PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT 388
Divertor Tokamak Test facility project: status of design and implementation 385
A method for on-line reactivity monitoring in nuclear reactors 383
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 382
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 375
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 352
Alternative definitions of kinetic parameters for accelerator driven systems 352
Assessment of the performance of the spectral element method applied to neutron transport problems 351
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 351
A method for the continuous monitoring of reactivity in subcritical source-driven systems 343
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 337
Assessment of an on-line reactivity monitoring technique 336
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 333
Integral parameters in source-driven systems 327
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 319
Neutronic Evaluations for the EVOL Molten Salt Reactor 317
Implementation of the quasi-static method for neutron transport 316
Integral neutron transport and new computational methods: a review 315
Alternative factorization methods for reactor kinetics 306
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 303
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 302
Evaluation of ray effects in linear transport problems 299
Evaluation of Ray Effects in Linear Transport Problems 293
Random effects on reactivity in molten salt reactors 290
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 289
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 286
Development of dynamic models for neutron transport calculations 284
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 284
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 278
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 274
The adjoint neutron transport equation and the statistical approach for its solution 273
On the spectrum of the multigroup diffusion equations 272
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 272
Reflector effects on the kinetic response in subcritical systems 272
Coupled dynamics in the physics of molten salt reactors 271
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 271
Dynamics of fluid fuel reactors in the presence of periodic perturbations 269
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 268
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 268
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 264
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 263
Assessment of a new method for reactivity measurement 262
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 261
Alternative Forms of the Time-Dependent Neutron Transport Equation 259
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 259
Computational Methods for Multidimensional Neutron Diffusion Problems 259
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 258
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 256
Performance of Non-Conventional Factorization Approaches for Neutron Kinetics 254
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 252
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 252
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 250
From transport to diffusion through a space asymptotic approach 249
Development of dynamic models for neutron transport calculations 248
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 248
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 247
XXI International Conference on Transport Theory 245
Analytical approach to the neutron kinetics of the non-homogeneous reactor 244
A method for reactivity monitoring in subcritical source-driven systems 244
Consistent multipoint kinetics for source-driven systems 241
Random Effects of Fissile Lumps in Molten Salt Reactors 241
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 241
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 241
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 240
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 240
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 239
Some Features of Spatial Neutron Kinetics for Multiplying Systems 237
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 236
General expression of the calibration curve for the CR-39 radon track detectors 234
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 234
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 233
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors 231
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 230
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 228
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 228
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 227
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 226
A cellular automaton model for offshore evacuation risk assessment 225
Numerical aspects in the study of neutron propagation 222
The quasi-static method revisited 220
Neutron kinetics of fluid-fuel systems by the quasi-static method 220
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 220
The time-dependent P1 model for the neutronics of multiplying systems: a review 217
The spectral element approach for the solution of neutron transport problems 217
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 217
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 216
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 215
The Neutronics of a Burning-Breeding Nuclear System 209
Transport Effects for Source-Oscillated Problems in Subcritical Systems 209
Nuclear engineering master thesis projects at Politecnico di Torino 208
The migration mode method in neutron transport theory 208
Nuclear data uncertainty quantification in the ARC fusion reactor 207
Methods in integral neutron transport 207
Interpretation of local flux measurements for reactivity prediction 207
Application of Spectral Elements for 1D Neutron Transport and comparison to Manufactured Solutions 207
Multiphysics approach to the analysis of molten salt reactors 206
Totale 27.412
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Categoria #
all - tutte 126.758
article - articoli 55.618
book - libri 0
conference - conferenze 67.076
curatela - curatele 770
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.093
Totale 252.315
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/20211.197 0 0 0 0 0 221 123 197 117 243 228 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
2023/20241.782 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
2025/20265.437 899 718 986 1.173 1.086 575 0 0 0 0 0 0
Totale 43.773