PORTO @ Archivio Istituzionale della Ricerca

DULLA, SANDRA
 Distribuzione geografica
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Continente #
EU - Europa 14.582
NA - Nord America 13.305
AS - Asia 2.674
SA - Sud America 205
AF - Africa 110
Continente sconosciuto - Info sul continente non disponibili 5
OC - Oceania 2
Totale 30.883
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Nazione #
US - Stati Uniti d'America 13.162
IT - Italia 4.275
DE - Germania 2.607
GB - Regno Unito 2.453
FR - Francia 1.936
CN - Cina 1.584
UA - Ucraina 967
TR - Turchia 410
IE - Irlanda 389
RU - Federazione Russa 327
SE - Svezia 285
CH - Svizzera 283
NL - Olanda 254
KR - Corea 221
BE - Belgio 188
FI - Finlandia 182
BR - Brasile 167
CA - Canada 127
AT - Austria 111
JP - Giappone 89
IN - India 68
AE - Emirati Arabi Uniti 66
HK - Hong Kong 60
IR - Iran 48
CI - Costa d'Avorio 44
ES - Italia 40
EU - Europa 36
AP - ???statistics.table.value.countryCode.AP??? 35
PK - Pakistan 34
RO - Romania 33
CZ - Repubblica Ceca 21
BG - Bulgaria 20
SG - Singapore 20
SN - Senegal 20
EG - Egitto 19
IL - Israele 19
VN - Vietnam 18
MY - Malesia 16
PT - Portogallo 16
SA - Arabia Saudita 16
AR - Argentina 15
NG - Nigeria 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
ID - Indonesia 6
JO - Giordania 6
PL - Polonia 6
EE - Estonia 5
NO - Norvegia 5
PH - Filippine 5
TH - Thailandia 4
KZ - Kazakistan 3
ZW - Zimbabwe 3
AU - Australia 2
CM - Camerun 2
GR - Grecia 2
GT - Guatemala 2
MN - Mongolia 2
ZA - Sudafrica 2
A2 - ???statistics.table.value.countryCode.A2??? 1
BD - Bangladesh 1
CY - Cipro 1
DZ - Algeria 1
EC - Ecuador 1
GH - Ghana 1
KG - Kirghizistan 1
LK - Sri Lanka 1
MA - Marocco 1
MO - Macao, regione amministrativa speciale della Cina 1
PE - Perù 1
SC - Seychelles 1
SY - Repubblica araba siriana 1
TN - Tunisia 1
VE - Venezuela 1
Totale 30.883
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Città #
Ashburn 3.461
Southend 2.193
Seattle 1.793
Chandler 980
Turin 823
Fairfield 663
Beijing 628
Princeton 615
Jacksonville 503
Ann Arbor 457
Torino 422
San Ramon 374
Dublin 367
Berlin 364
Woodbridge 357
Houston 312
Izmir 297
Wilmington 281
Cambridge 279
Council Bluffs 271
Shanghai 268
Zhengzhou 246
Bern 236
Milan 213
San Donato Milanese 179
Chicago 173
Helsinki 151
San Mauro Torinese 150
Brussels 137
Baltimore 129
Zaporozhye 124
Pennsylvania Furnace 117
Vienna 113
Overberg 104
Rome 103
Saint Petersburg 96
Bologna 95
Boardman 88
Redwood City 77
Mountain View 69
Monopoli 66
Hefei 65
Abu Dhabi 59
Bremen 54
Padua 54
Gif-sur-yvette 50
Hangzhou 50
Paris 47
Abidjan 44
Malatya 42
Guangzhou 41
Redmond 41
Toronto 41
Atlanta 36
San Diego 35
Falls Church 33
New York 33
Porto Alegre 33
Genova 31
Moscow 30
Genoa 29
Harbin 28
Islamabad 28
Istanbul 28
Menlo Park 27
Norwalk 27
Shenzhen 27
London 26
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
Amsterdam 20
Andover 20
Putian 20
Montréal 19
San Antonio 19
Aix-en-provence 18
Sofia 18
Xian 18
Grottaferrata 17
Miami 17
Sao Paulo 17
Kunming 16
Phoenix 16
Verzuolo 16
Berkeley 15
Hanoi 15
Pisa 15
Catania 14
Fuzhou 14
Lagos 14
Lappeenranta 14
Totale 20.011
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 519
Study of a low-power, fast-neutron-based ADS 361
A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors 321
PROGRESS IN MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED FAST REACTORS 314
A method for on-line reactivity monitoring in nuclear reactors 306
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 300
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 300
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 295
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 289
Implementation of the quasi-static method for neutron transport 286
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 283
Assessment of the performance of the spectral element method applied to neutron transport problems 281
A method for the continuous monitoring of reactivity in subcritical source-driven systems 271
PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT 271
Alternative definitions of kinetic parameters for accelerator driven systems 268
Alternative factorization methods for reactor kinetics 266
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 265
Assessment of an on-line reactivity monitoring technique 263
Integral parameters in source-driven systems 257
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 253
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 250
Integral neutron transport and new computational methods: a review 249
Neutronic Evaluations for the EVOL Molten Salt Reactor 244
Evaluation of ray effects in linear transport problems 239
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 238
Development of dynamic models for neutron transport calculations 236
An analytical solution of the point kinetics equations with time variable reactivity by the decomposition method 234
Alternative Forms of the Time-Dependent Neutron Transport Equation 233
Computational Methods for Multidimensional Neutron Diffusion Problems 231
Evaluation of Ray Effects in Linear Transport Problems 230
Coupled dynamics in the physics of molten salt reactors 230
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 224
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 224
Performance of Non-Conventional Factorization Approaches for Neutron Kinetics 222
Random effects on reactivity in molten salt reactors 222
Development of dynamic models for neutron transport calculations 220
Analytical Solutions to some Neutron Transport Problems in the Spirit of Silvio E. Corno’s Teachings 219
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 219
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 219
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 218
From transport to diffusion through a space asymptotic approach 217
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 215
Dynamics of fluid fuel reactors in the presence of periodic perturbations 214
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 214
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 213
Analytical approach to the neutron kinetics of the non-homogeneous reactor 211
An Analytical Solution of the Point Kinetics Equations with Time Variable Reactivity by the Decomposition Method 211
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 210
On the spectrum of the multigroup diffusion equations 209
The adjoint neutron transport equation and the statistical approach for its solution 207
Numerical aspects in the study of neutron propagation 205
Consistent multipoint kinetics for source-driven systems 204
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 204
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 203
ANALYSIS OF TRITIUM EXTRACTION SYSTEM FOR LITHIUM-LEAD EU DEMO BLANKET DESIGNS USING PERMEATOR AGAINST VACUUM 201
COMPARISON OF DIRECT AND QUASI-STATIC METHODS FOR NEUTRON KINETIC CALCULATIONS WITH THE EDF R&D COCAGNE CODE 200
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 199
Reflector effects on the kinetic response in subcritical systems 199
Some Features of Spatial Neutron Kinetics for Multiplying Systems 198
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 198
Comparative assessment of methods for the reactivity measurement in subcritical systems by pulsed experiments 198
Quasi-Static Method for the Time-Dependent Neutronics of Fluid-Fuel Systems 198
A cellular automaton model for offshore evacuation risk assessment 197
XXI International Conference on Transport Theory 194
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 193
FEEDBACK EFFECTS IN THE DYNAMICS OF MOLTEN SALT REACTORS 191
The quasi-static method revisited 191
Assessment of a new method for reactivity measurement 191
General expression of the calibration curve for the CR-39 radon track detectors 191
Full-core coupled neutronic/thermal-hydraulic modelling of GEN-IV LMFBRs 191
The time-dependent P1 model for the neutronics of multiplying systems: a review 190
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 189
Neutron kinetics of fluid-fuel systems by the quasi-static method 189
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 188
NEURAL NETWORK AND AREA METHOD INTERPRETATION OF PULSED EXPERIMENTS 186
The spectral element approach for the solution of neutron transport problems 184
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 182
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 182
Multiphysics approach to the analysis of molten salt reactors 179
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 179
On Some Features of Spatial Neutron Kinetics for Multiplying Systems 177
Random Effects of Fissile Lumps in Molten Salt Reactors 177
Nuclear engineering master thesis projects at Politecnico di Torino 173
Transport Effects for Source-Oscillated Problems in Subcritical Systems 172
Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods 172
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 171
The migration mode method in neutron transport theory 171
Transport Effects for Source-Oscillated Problems in Subcritical Systems 171
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 169
Reactivity oscillations in molten salt reactors 167
On the exact solution for the multi-group kinetic neutron diffusion equation in a rectangle 166
Analysis of the Role of Fluid-Dynamic Phenomena in the Neutronics of Molten-Salt Systems 166
A method for reactivity monitoring in subcritical source-driven systems 165
Nuclear engineering education in Italian universities 164
Reactivity Determination for Subcritical Systems by Source-Pulsed Experiments 164
A space asymptotic approach to some neutron transport problems 163
The quasi-static method for nuclear reactor kinetics: a review and a look ahead 162
Performance and convergence issue of coarse-mesh methods for diffusion calculations 162
Models for the Interpretation of Local Flux Measurements in Subcritical Systems 161
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 160
Totale 21.838
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Categoria #
all - tutte 81.865
article - articoli 34.144
book - libri 0
conference - conferenze 45.192
curatela - curatele 564
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 1.494
Totale 163.259
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2018/20191.394 0 0 0 0 0 0 0 0 0 376 601 417
2019/20202.812 312 181 74 310 296 291 156 393 342 293 101 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
2023/20241.198 63 321 82 106 128 160 89 91 116 42 0 0
Totale 31.189