PORTO @ Archivio Istituzionale della Ricerca

DULLA, SANDRA
 Distribuzione geografica
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Continente #
NA - Nord America 20.145
EU - Europa 17.813
AS - Asia 12.353
SA - Sud America 1.279
AF - Africa 221
OC - Oceania 11
Continente sconosciuto - Info sul continente non disponibili 6
Totale 51.828
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Nazione #
US - Stati Uniti d'America 19.847
IT - Italia 5.260
SG - Singapore 3.318
CN - Cina 3.039
DE - Germania 2.838
VN - Vietnam 2.820
GB - Regno Unito 2.558
FR - Francia 2.243
RU - Federazione Russa 1.394
BR - Brasile 1.057
UA - Ucraina 989
KR - Corea 802
HK - Hong Kong 508
TR - Turchia 481
IE - Irlanda 396
IN - India 351
NL - Olanda 330
CH - Svizzera 304
SE - Svezia 301
FI - Finlandia 300
BE - Belgio 234
CA - Canada 209
JP - Giappone 182
AT - Austria 166
BD - Bangladesh 114
ES - Italia 106
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
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 9
CR - Costa Rica 8
JM - Giamaica 8
SY - Repubblica araba siriana 8
DO - Repubblica Dominicana 7
DZ - Algeria 7
GR - Grecia 7
OM - Oman 7
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
HN - Honduras 3
PS - Palestinian Territory 3
TG - Togo 3
TT - Trinidad e Tobago 3
ZW - Zimbabwe 3
AO - Angola 2
Totale 51.792
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Città #
Ashburn 4.090
Southend 2.193
Singapore 1.879
Seattle 1.800
Turin 1.187
San Jose 1.042
Chandler 980
Beijing 886
Ho Chi Minh City 704
Council Bluffs 702
Fairfield 663
Hanoi 660
Princeton 615
Santa Clara 511
Jacksonville 504
Ann Arbor 457
Torino 422
Dublin 374
San Ramon 374
Berlin 367
Hong Kong 361
Woodbridge 357
Dallas 334
Houston 326
Seoul 316
Milan 311
Boardman 309
Izmir 301
Shanghai 301
Cambridge 289
Wilmington 282
Zhengzhou 260
Bern 236
Los Angeles 227
Helsinki 196
Lauterbourg 193
Chicago 188
San Donato Milanese 179
Brussels 175
Hefei 170
Rome 163
San Mauro Torinese 150
Da Nang 139
Baltimore 132
Vienna 131
Zaporozhye 124
Bologna 118
Pennsylvania Furnace 117
Haiphong 115
Moscow 111
New York 109
Overberg 104
Saint Petersburg 96
Munich 81
Buffalo 79
Redwood City 77
Frankfurt am Main 74
São Paulo 71
Mountain View 69
Tokyo 69
Columbus 68
Guangzhou 68
Monopoli 66
Abu Dhabi 62
Istanbul 59
The Dalles 58
Paris 57
Lappeenranta 55
Bremen 54
Padua 54
Piscataway 54
Toronto 54
Hangzhou 53
Atlanta 50
Gif-sur-yvette 50
Orem 50
Genoa 49
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
Montreal 36
Washington 36
Bangkok 35
Nuremberg 35
San Diego 35
Falls Church 33
Genova 31
Palermo 31
Changsha 29
Chennai 29
Phoenix 29
Totale 29.676
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Nome #
Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient 689
Divertor Tokamak Test facility project: status of design and implementation 535
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 443
PRELIMINARY FUNCTIONAL SAFETY ASSESSMENT FOR MOLTEN SALT FAST REACTORS IN THE FRAMEWORK OF THE SAMOFAR PROJECT 432
A method for on-line reactivity monitoring in nuclear reactors 419
New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal method 413
Tritium extraction from lithium-lead in the EU DEMO blanket using Permeator Against Vacuum 412
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 401
Assessment of an on-line reactivity monitoring technique 397
Spatial and Spectral Effects in Subcritical System Pulsed Experiments 389
Analysis of KUCA measurements by the reactivity monitoring MAρTA method 389
Assessment of the performance of the spectral element method applied to neutron transport problems 380
Alternative definitions of kinetic parameters for accelerator driven systems 373
Neutronic Evaluations for the EVOL Molten Salt Reactor 367
Propagation phenomena in the kinetics of source-driven systems with a continuous slowing-down model 362
Integral parameters in source-driven systems 360
Benchmark of Dynamic Simulation Tools for Molten Salt Reactors 359
Full-Core Coupled Neutronic/Thermal-Hydraulic Model of Innovative Lead-Cooled Fast Reactors 349
Integral neutron transport and new computational methods: a review 343
Implementation of the quasi-static method for neutron transport 342
Reflector effects on the kinetic response in subcritical systems 342
Evaluation of the neutron activation of JET in-vessel components following DT irradiation 341
A Genetic-Driven Optimization of the Energy Grid Structure for Nodal Full-Core Calculations in Lead-Cooled Fast Reactors 335
An OpenFOAM solver for multiphysics modeling of fusion reactor design: The nemoFoam code 332
Alternative factorization methods for reactor kinetics 331
Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems 331
Evaluation of Ray Effects in Linear Transport Problems 329
Evaluation of ray effects in linear transport problems 326
Development of a hybrid deterministic/stochastic method for 1D nuclear reactor kinetics 325
The Spectral Element Method for Static Neutron Transport in AN Approximation. Part II 322
Validation of the MARTA reactivity monitoring technique using a boiling water reactor turbine trip benchmark 319
Development of dynamic models for neutron transport calculations 317
Random effects on reactivity in molten salt reactors 311
An intrinsically safe facility for forefront research and training on nuclear technologies —Kinetics and dynamics 310
The Spectral Element Method for Static Neutron Transport in A_N Approximation. Part I 307
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
Cutting-edge R&D activities of CIRTEN in support of the Technology Park annexed to the Italian National Repository of radioactive waste 302
Interpretation of experimental measurements on the SC-1 configuration of the VENUS-F core 302
Analytical Benchmarks for the Kinetics of Accelerator-Driven systems 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 300
A method for reactivity monitoring in subcritical source-driven systems 298
Coupled dynamics in the physics of molten salt reactors 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 295
Non-intrusive Uncertainty Propagation in the ARC Fusion Reactor through the nemoFOAM Multi-physics Tool 294
On the spectrum of the multigroup diffusion equations 290
Adaptive time step selection in the quasi-static methods of nuclear reactor dynamics 290
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 286
Computational Methods for Multidimensional Neutron Diffusion Problems 286
Reduction of spatial and spectral effects by adjoint weighting of flux signals in a reactivity reconstruction technique 285
Interpretation of Local FluxMeasurements in Subcritical Systemsand Reactivity Determination 285
From transport to diffusion through a space asymptotic approach 283
THE PROBLEM OF THE FORMULATION OF INTEGRAL PARAMETERS IN SOURCE-DRIVEN SYSTEMS: A CRITICAL EVALUATION 282
Neutronic Analysis of the Fusion Reactor ARC: Monte Carlo Simulations with the Serpent Code 282
XXI International Conference on Transport Theory 280
Models and methods for the representation of decay and photon heat in spatial kinetics calculations 280
Interaction between Fluid-Dynamics and Neutronic Phenomena in the Physics of Molten-Salt Systems 278
Neutron kinetic calculations using a quasi-static method with the COCAGNE code 273
On the Evaluation of Ray Effects in Multidimensional and Time-Dependent Transport Problems 273
Development of dynamic models for neutron transport calculations 273
Some Features of Spatial Neutron Kinetics for Multiplying Systems 272
Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics 272
Alternative Forms of the Time-Dependent Neutron Transport Equation 272
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 266
MULTI-PHYSICS MODELING OF INNOVATIVE LEAD-COOLED NUCLEAR FAST REACTORS 266
Random Effects of Fissile Lumps in Molten Salt Reactors 262
Genetic algorithm-based optimisation of the few-group structure for lead fast reactor analysis 261
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
Consistent multipoint kinetics for source-driven systems 260
A Nonintrusive Nuclear Data Uncertainty Propagation Study for the ARC Fusion Reactor Design 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
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods 255
A cellular automaton model for offshore evacuation risk assessment 254
Analytical Solution to Discrete Ordinate Time Dependent Transport Problems 253
The time-dependent P1 model for the neutronics of multiplying systems: a review 251
The quasi-static method revisited 250
REPORT ON INTERMEDIATE RESULTS OF THE IAEA CRP ON STUDIES OF ADVANCED REACTOR TECHNOLOGY OPTIONS FOR EFFECTIVE INCINERATION OF RADIOACTIVE WASTES 250
Nuclear data uncertainty quantification in the ARC fusion reactor 249
Effects of neutron source characteristics in direct and adjoint problems for subcritical systems 245
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed 245
“On the Foundation of Transport-Driven Diffusion for Neutron Transport Problems” 244
The spectral element approach for the solution of neutron transport problems 243
A methodology for the identification of the postulated initiating events of the Molten Salt Fast Reactor 242
A response matrix formulation of multidimensional transport problems 240
The migration mode method in neutron transport theory 240
Methods in integral neutron transport 239
Multiphysics approach to the analysis of molten salt reactors 238
Nuclear engineering master thesis projects at Politecnico di Torino 238
Totale 31.004
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Categoria #
all - tutte 142.200
article - articoli 62.779
book - libri 0
conference - conferenze 74.907
curatela - curatele 830
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 2.255
Totale 282.971
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202168 0 0 0 0 0 0 0 0 0 0 0 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
2025/202613.878 899 718 986 1.173 1.086 833 2.010 1.124 3.107 1.478 356 108
Totale 52.214