RE.PUBLIC@POLIMI pubblicazioni di ricerca del Politecnico di Milano

PELLEGRINI, MARCO
 Distribuzione geografica
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Continente #
AS - Asia 2.161
EU - Europa 1.640
NA - Nord America 1.212
SA - Sud America 533
AF - Africa 61
Continente sconosciuto - Info sul continente non disponibili 3
Totale 5.610
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Nazione #
RU - Federazione Russa 1.256
US - Stati Uniti d'America 1.146
CN - Cina 942
SG - Singapore 643
BR - Brasile 431
VN - Vietnam 187
IT - Italia 121
JP - Giappone 111
KR - Corea 96
DE - Germania 52
AR - Argentina 50
HK - Hong Kong 38
CI - Costa d'Avorio 35
CA - Canada 30
ID - Indonesia 30
FI - Finlandia 29
IN - India 29
GB - Regno Unito 28
MX - Messico 25
NL - Olanda 23
FR - Francia 21
UA - Ucraina 21
EC - Ecuador 19
SE - Svezia 19
BD - Bangladesh 16
IE - Irlanda 13
AT - Austria 12
TR - Turchia 12
IQ - Iraq 11
PL - Polonia 11
ES - Italia 10
JO - Giordania 9
CO - Colombia 8
PY - Paraguay 8
CH - Svizzera 7
CL - Cile 7
ZA - Sudafrica 7
IR - Iran 6
MA - Marocco 6
UY - Uruguay 5
KZ - Kazakistan 4
PK - Pakistan 4
EG - Egitto 3
MY - Malesia 3
NP - Nepal 3
SN - Senegal 3
UZ - Uzbekistan 3
AL - Albania 2
AZ - Azerbaigian 2
CR - Costa Rica 2
CZ - Repubblica Ceca 2
DK - Danimarca 2
DO - Repubblica Dominicana 2
EU - Europa 2
GT - Guatemala 2
NG - Nigeria 2
NI - Nicaragua 2
RO - Romania 2
VE - Venezuela 2
AE - Emirati Arabi Uniti 1
AM - Armenia 1
BE - Belgio 1
BO - Bolivia 1
CM - Camerun 1
DZ - Algeria 1
EE - Estonia 1
GA - Gabon 1
GF - Guiana Francese 1
HR - Croazia 1
IL - Israele 1
JM - Giamaica 1
KE - Kenya 1
KW - Kuwait 1
KY - Cayman, isole 1
LT - Lituania 1
LV - Lettonia 1
MK - Macedonia 1
NO - Norvegia 1
PE - Perù 1
PS - Palestinian Territory 1
QA - Qatar 1
RS - Serbia 1
SA - Arabia Saudita 1
SI - Slovenia 1
SY - Repubblica araba siriana 1
TH - Thailandia 1
TJ - Tagikistan 1
TN - Tunisia 1
TT - Trinidad e Tobago 1
TW - Taiwan 1
XK - ???statistics.table.value.countryCode.XK??? 1
YE - Yemen 1
Totale 5.610
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Città #
Hefei 502
Singapore 477
Ashburn 261
Moscow 171
Seoul 82
Beijing 78
Kent 70
Tokyo 70
Ho Chi Minh City 67
Chandler 66
Santa Clara 55
Los Angeles 45
Hanoi 37
Ann Arbor 36
Hong Kong 33
Abidjan 32
Milan 32
Buffalo 30
Redondo Beach 28
São Paulo 25
Woodbridge 25
Fairfield 24
Houston 21
Hangzhou 20
Council Bluffs 19
Dallas 19
Boardman 17
Karlsruhe 17
Wilmington 17
Shanghai 15
Mexico City 14
Cambridge 13
Dublin 13
Seattle 13
Brasília 12
Dearborn 12
Helsinki 12
New York 12
Ottawa 12
Rio de Janeiro 12
Frankfurt am Main 11
Lawrence 10
Medford 10
Amman 9
Belo Horizonte 9
Biên Hòa 9
Haiphong 9
Porto Alegre 9
Zhengzhou 9
Buenos Aires 8
Chicago 8
Curitiba 8
Genoa 8
Harbin 8
Turin 8
Baghdad 7
Campinas 7
Jakarta 7
Mountain View 7
Redwood City 7
Tianjin 7
Vienna 7
Des Moines 6
Guarulhos 6
Pisa 6
Quito 6
Salvador 6
The Dalles 6
Toronto 6
Wuhan 6
Asunción 5
Biassono 5
Da Nang 5
Guayaquil 5
Jacksonville 5
Montevideo 5
Montreal 5
Nuremberg 5
Orem 5
Shijiazhuang 5
Warsaw 5
Amsterdam 4
Aracaju 4
Bắc Giang 4
Caxias do Sul 4
Chennai 4
Cotia 4
Daejeon 4
Denver 4
Dhaka 4
Dong Ket 4
Hebei 4
Istanbul 4
Kitashinjuku 4
London 4
Maceió 4
Quận Bình Thạnh 4
Recife 4
Rome 4
Salt Lake City 4
Totale 2.877
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Nome #
Acknowledgement to reviewers of fluids in 2018 193
Modelling of Multi-Physics Phenomena in Fast Reactor Design: Safety and Experimental Validation 166
Suppression pool testing at the SIET labs (2) Steam chugging investigation under the presence of non-condensable gas in a vertical opened pipe 159
Suppression pool testing at the SIET laboratory (1) Experimental Investigation of Critical Phenomena Expected in the Fukushima Daiichi Suppression Chamber 152
Direct contact condensation experiments for clarification of S/C temperature evolution during long term steam discharge 149
Suppression pool testing at the SIET laboratory: experimental investigation of critical phenomena expected in the Fukushima Daiichi suppression chamber 134
Preliminary Considerations from the 2nd Phase of Experiments at the SIET/SWAM Facility 128
Suppression pool testing at the SIET labs (3) Experiments on Steam Direct Contact Condensation in a Vertical Multi-holes Sparger 117
Investigation of jet induced by direct contact condensation using PIV 112
Validation of the SAMPSON/MCRA Code against CORA-18 Experiment 87
Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1 82
Extended development of a bubble percolation method to predict boiling crisis of flow boiling 79
UNSTEADY CFD ANALYSIS OF PARALLEL JET MIXING AS A SUPPORT OF THE IRIS STEAM GENERATOR OUTLET DESIGN 77
Transient behaviour and heat transfer characteristics in debris beds: Simulation and analysis of the LIVEJ2 experiment 76
Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method 70
Analysis of accident progression of Fukushima Daiichi NPPS with Sampson code 67
Analysis of melt progression and debris cooling at the Fukushima Daiichi unit 3 by the Sampson Code 66
CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined 66
Study on the difference between B4C powder and B4C pellet regarding the eutectic reaction with stainless steel 66
Analysis of accident progression of Fukushima Daiichi NPP by the sampson code 65
A numerical study on turbulence attenuation model for liquid droplet impingement erosion 65
Algebraic turbulent heat flux model for prediction of thermal stratification in piping systems 64
An approach toward evaluation of fp behavior in npps under severe accidents 64
An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident 62
Benchmark study of the accident at the fukushima daiichi NPS best estimate case comparison 62
Prediction of thermal stratification in a u-bent pipe: A URANS validation 62
Accident analysis of Fukushima Daiichi nuclear power plant unit 2 by the SAMPSON severe accident code 62
Validation and application of numerical modeling for in-vessel melt retention in corium pools 61
Code to code model comparison analysis of Sampson with Melcor for core degradation progression against Fukushima Daiichi NPP UN-1 accident 61
A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics 60
On the interaction of boundary layer and mixing layer in stratified pipe flow 59
Eutectic melting and relocation behavior of B4C pellet-stainless steel under radiative heating 59
Radiation Heating Effects on B4C-SS Eutectic Melting and Its Relocation Behaviour 59
Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere 59
A quantitative method of eutectic reaction study between boron carbide and stainless steel 59
Main Outputs from the OECD/NEA ARC-F Project 58
Analysis of the Long Term Interaction Between Molten Core And Dry Concrete At Fukushima Daiichi Unit 1 58
Modeling of Multi-Physics Phenomena in Fast Reactors Design/Safety and Experimental Validation 57
Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections 56
Simulation of the LIVE-J experiments using MELCOR: findings and current limitations 55
EULERIAN TWO-PHASE FLOW MODELING OF STEAM DIRECT CONTACT CONDENSATION FOR THE FUKUSHIMA ACCIDENT INVESTIGATION 54
Numerical analysis of thermally stratified flow in horizontal pipe with upward bend 54
Accident analysis of Fukushima Daiichi nuclear power plant unit 1 by the sampson severeaccidentcode 54
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project 53
Evaluation of Molten Corium Spreading and Sedimentation Behaviors Within Primary Containment Vessel in Unit 3 of Fukushima Daiichi Nuclear Power Plant Toward the Best Prediction of Fuel Debris Distribution 53
Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (4) Analyzing Eutectic Melting and Relocation Dynamics in B4C-Stainless Steel Using the Moving Particle Semi-Implicit (MPS) Method 53
Analysis of accident progression with the SAMPSON code in Fukushima Daiichi nuclear power plant unit 2 53
Visualization Experiments of Radiation Heating on the Eutectic Reaction Between B4C-SS and Its Relocation Behavior 51
Model uncertainty quantification for fuel rod damage evaluation in SFRs 51
Thermophoretic Particle Deposition: A Computational Fluid Dynamics Approach for Estimating Hotspots 51
Molten core relocation analysis of Cora-17 And Cora-18 for the SAMPSON/MCRA validation 51
The findings obtained during the OECD/NEA BSAF activity with the employment of the Sampson code 50
Numerical investigation of bent pipe flows at transitional Reynolds number 50
Study on general wall damping functions definition: A low reynolds number bounded flows validation 49
Analysis of accident progression of Fukushima Dai-ichi with SAMPSON Code - (3) UNIT 3 49
Melt progression analysis of TEPCO's Fukushima Daiichi Unit 3 by the SAMPSON Code 48
Improving accuracy of CFD modelling for direct contact condensation in a suppression pool 48
Early phase accident progression analysis of Fukushima Daiichi unit 3 by the SAMPSON code 48
Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – Overview and first results 48
Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (1) Project Overview and Progress Until 2022 47
On the CSAU employment during ULOF accident initiating phase for sodium-cooled fast reactors 47
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm 46
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project 46
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 3 46
Radioactive Aerosol Control and Decontamination in the Decommissioning of the Fukushima Daiichi Nuclear Power Station 46
The Development of a Multiphysics Coupled Solver for Studying the Effect of Dynamic Heterogeneous Configuration on Particulate Debris Bed Criticality and Cooling Characteristics 45
Suppression pool thermal-hydraulics preliminary analysis of fukushima daiichi unit-2 using pool-3D module of Sampson code 45
Conversion factors bridging radiocative fission product distributions in the primary containment vessel of Fukushima daiichi npp and dose rates measured by the containment atmosphere monitoring system 45
Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project 44
VALIDATION OF SPARC-90 POOL SCRUBBING MODEL IN SEVERE ACCIDENT CODE 44
Revolatilization of iodine by bubbly flow in the suppression pool during an accident 44
Eulerian two-phase flow modeling of steam direct contact condensation for the fukushima accident investigation 44
Preliminary ex-vessel sensitivity study of Fukushima Dai-Ichi unit 1 using DSA1 and CVPA coupling modules of the Sampson Code 44
Benchmark study of the accident at the Fukushima Daiichi NPS: Best-estimate case comparison 44
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – Results of severe accident analyses for Unit 1 42
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2 42
Melting test of penetrating tube through BWR-RPV bottom wall 41
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3 41
Three weeks analysis of the Fukushima Daiichi unit 3 NPP by the Sampson code: Contribution to the BSAF-2 project 41
State of SAMPSON code development for the analysis of Fukushima Daiichi severe accident 41
INVESTIGATION ON AEROSOL SPRAY SCAVENGING BY USING A MULTI-HOLE NOZZLE WITH WATER MIST FOR DECOMMISSIONING OF FUKUSHIMA DAIICHI POWER PLANTS 41
Integral severe accident codes: IMPACT/SAMPSON 41
Validation and application of a new reflooding model for the Sampson Code 39
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), phase 2 – Results of severe accident analyses for unit 2 39
Modeling of Rayleigh-Taylor instability for steam direct contact condensation 39
Simulation analysis on accident at Fukushima Daiichi Nuclear Power Plant unit 2 by sampson code 39
Development and Modification of Pool Scrubbing Decontamination Factor Evaluation in Severe Accident Code 38
Overview and outcomes of the OECD/NEA Benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3 37
Confirmation of severe accident code modeling in light of the findings at Fukushima Daiichi NPPs 37
Three weeks analysis of the Fukushima Daiichi Unit 3 NPP by the SAMPSON code: Contribution to the BSAF-2 project 37
PIV Investigation of Jet Mixing Induced by Direct Contact Condensation 36
Overview and outcomes of the OECD/NEA Benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 2 35
Investigating eutectic behavior and material relocation in B4C-stainless steel composites using the improved MPS method 35
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) Phase 2 – Results of severe accident analyses for Unit 1 32
Totale 5.731
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Categoria #
all - tutte 12.476
article - articoli 5.543
book - libri 0
conference - conferenze 6.840
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 93
Totale 24.952
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202149 0 0 0 0 0 7 3 4 2 13 6 14
2021/202292 7 13 5 5 7 17 2 4 2 7 4 19
2022/2023191 15 2 10 20 22 22 6 16 33 12 11 22
2023/202464 12 14 1 9 4 5 1 1 3 4 0 10
2024/2025715 8 4 6 7 55 46 14 45 51 87 79 313
2025/20264.205 873 1.331 715 902 253 131 0 0 0 0 0 0
Totale 5.731