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

PELLEGRINI, MARCO
 Distribuzione geografica
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Continente #
AS - Asia 3.616
NA - Nord America 2.301
EU - Europa 1.954
SA - Sud America 573
AF - Africa 80
Continente sconosciuto - Info sul continente non disponibili 3
OC - Oceania 1
Totale 8.528
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Nazione #
US - Stati Uniti d'America 2.208
CN - Cina 1.360
RU - Federazione Russa 1.259
SG - Singapore 1.002
BR - Brasile 466
VN - Vietnam 340
JP - Giappone 309
KR - Corea 287
IT - Italia 251
FR - Francia 110
HK - Hong Kong 85
DE - Germania 77
AR - Argentina 51
CA - Canada 46
GB - Regno Unito 44
IN - India 40
FI - Finlandia 38
CI - Costa d'Avorio 35
NL - Olanda 34
MX - Messico 33
ID - Indonesia 32
BD - Bangladesh 26
SE - Svezia 23
UA - Ucraina 23
EC - Ecuador 21
IQ - Iraq 17
PL - Polonia 17
ES - Italia 15
AT - Austria 14
IE - Irlanda 14
TR - Turchia 14
PK - Pakistan 13
TW - Taiwan 13
ZA - Sudafrica 13
JO - Giordania 11
PY - Paraguay 9
CL - Cile 8
CO - Colombia 8
IR - Iran 8
MA - Marocco 8
CH - Svizzera 7
SA - Arabia Saudita 7
PH - Filippine 6
MY - Malesia 5
SN - Senegal 5
TH - Thailandia 5
UY - Uruguay 5
AZ - Azerbaigian 4
DK - Danimarca 4
KZ - Kazakistan 4
NP - Nepal 4
RO - Romania 4
UZ - Uzbekistan 4
AE - Emirati Arabi Uniti 3
AL - Albania 3
CR - Costa Rica 3
CZ - Repubblica Ceca 3
DO - Repubblica Dominicana 3
EG - Egitto 3
KE - Kenya 3
OM - Oman 3
PS - Palestinian Territory 3
TN - Tunisia 3
DZ - Algeria 2
EU - Europa 2
GR - Grecia 2
GT - Guatemala 2
JM - Giamaica 2
LT - Lituania 2
NG - Nigeria 2
NI - Nicaragua 2
PT - Portogallo 2
SY - Repubblica araba siriana 2
TJ - Tagikistan 2
VE - Venezuela 2
AM - Armenia 1
BE - Belgio 1
BH - Bahrain 1
BO - Bolivia 1
CG - Congo 1
CM - Camerun 1
EE - Estonia 1
ET - Etiopia 1
GA - Gabon 1
GF - Guiana Francese 1
HR - Croazia 1
IL - Israele 1
KW - Kuwait 1
KY - Cayman, isole 1
LV - Lettonia 1
LY - Libia 1
MK - Macedonia 1
MM - Myanmar 1
MU - Mauritius 1
NO - Norvegia 1
NZ - Nuova Zelanda 1
PE - Perù 1
QA - Qatar 1
RS - Serbia 1
SI - Slovenia 1
Totale 8.525
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Città #
Singapore 647
Hefei 507
San Jose 445
Ashburn 357
Seoul 266
Tokyo 258
Moscow 172
Milan 139
Ho Chi Minh City 122
Beijing 107
North Charleston 107
Lauterbourg 81
Hong Kong 72
Kent 70
Santa Clara 69
Hanoi 68
Chandler 66
Dallas 65
Los Angeles 63
Las Vegas 56
Council Bluffs 46
Ann Arbor 36
Shanghai 35
São Paulo 33
Abidjan 32
The Dalles 32
Buffalo 31
Hangzhou 30
Frankfurt am Main 28
Redondo Beach 28
Woodbridge 25
Fairfield 24
Houston 24
New York 23
Helsinki 21
Sacramento 21
Atlanta 18
Guangzhou 18
Mexico City 18
Wuhan 18
Boardman 17
Haiphong 17
Karlsruhe 17
Wilmington 17
Salt Lake City 16
Zhengzhou 16
Harbin 15
Shijiazhuang 15
Changsha 14
Dublin 14
Orem 14
Cambridge 13
Chengdu 13
Rio de Janeiro 13
Seattle 13
Brasília 12
Chicago 12
Dearborn 12
Ottawa 12
Belo Horizonte 11
Genoa 11
Tianjin 11
Warsaw 11
Amman 10
Baghdad 10
Lawrence 10
Medford 10
Montreal 10
Turin 10
Biên Hòa 9
Chennai 9
Curitiba 9
Porto Alegre 9
Vienna 9
Amsterdam 8
Buenos Aires 8
Da Nang 8
Denver 8
Jakarta 8
London 8
Shenzhen 8
São José dos Campos 8
Taipei 8
Toronto 8
Campinas 7
Mountain View 7
Nuremberg 7
Phoenix 7
Redwood City 7
Salvador 7
Brooklyn 6
Des Moines 6
Dhaka 6
Guarulhos 6
Guayaquil 6
Johannesburg 6
Manchester 6
Pisa 6
Quito 6
Rome 6
Totale 4.881
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Nome #
Acknowledgement to reviewers of fluids in 2018 248
Validation of the SAMPSON/MCRA Code against CORA-18 Experiment 216
Modelling of Multi-Physics Phenomena in Fast Reactor Design: Safety and Experimental Validation 207
Direct contact condensation experiments for clarification of S/C temperature evolution during long term steam discharge 191
Suppression pool testing at the SIET labs (2) Steam chugging investigation under the presence of non-condensable gas in a vertical opened pipe 190
Suppression pool testing at the SIET laboratory (1) Experimental Investigation of Critical Phenomena Expected in the Fukushima Daiichi Suppression Chamber 183
Preliminary Considerations from the 2nd Phase of Experiments at the SIET/SWAM Facility 183
Suppression pool testing at the SIET laboratory: experimental investigation of critical phenomena expected in the Fukushima Daiichi suppression chamber 166
Suppression pool testing at the SIET labs (3) Experiments on Steam Direct Contact Condensation in a Vertical Multi-holes Sparger 161
Investigation of jet induced by direct contact condensation using PIV 139
Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1 130
Transient behaviour and heat transfer characteristics in debris beds: Simulation and analysis of the LIVEJ2 experiment 120
CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined 111
Validation and application of numerical modeling for in-vessel melt retention in corium pools 110
UNSTEADY CFD ANALYSIS OF PARALLEL JET MIXING AS A SUPPORT OF THE IRIS STEAM GENERATOR OUTLET DESIGN 108
Extended development of a bubble percolation method to predict boiling crisis of flow boiling 107
Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method 106
Analysis of the Long Term Interaction Between Molten Core And Dry Concrete At Fukushima Daiichi Unit 1 104
Analysis of melt progression and debris cooling at the Fukushima Daiichi unit 3 by the Sampson Code 102
Study on the difference between B4C powder and B4C pellet regarding the eutectic reaction with stainless steel 102
Main Outputs from the OECD/NEA ARC-F Project 101
Analysis of accident progression of Fukushima Daiichi NPPS with Sampson code 100
An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident 97
An approach toward evaluation of fp behavior in npps under severe accidents 94
Analysis of accident progression of Fukushima Daiichi NPP by the sampson code 93
Algebraic turbulent heat flux model for prediction of thermal stratification in piping systems 93
A numerical study on turbulence attenuation model for liquid droplet impingement erosion 93
A quantitative method of eutectic reaction study between boron carbide and stainless steel 91
Eutectic melting and relocation behavior of B4C pellet-stainless steel under radiative heating 90
Radiation Heating Effects on B4C-SS Eutectic Melting and Its Relocation Behaviour 90
Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere 90
Benchmark study of the accident at the fukushima daiichi NPS best estimate case comparison 89
Thermophoretic Particle Deposition: A Computational Fluid Dynamics Approach for Estimating Hotspots 87
A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics 87
Accident analysis of Fukushima Daiichi nuclear power plant unit 2 by the SAMPSON severe accident code 87
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 86
Accident analysis of Fukushima Daiichi nuclear power plant unit 1 by the sampson severeaccidentcode 85
Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections 85
Visualization Experiments of Radiation Heating on the Eutectic Reaction Between B4C-SS and Its Relocation Behavior 84
On the interaction of boundary layer and mixing layer in stratified pipe flow 84
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project 84
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 84
Prediction of thermal stratification in a u-bent pipe: A URANS validation 84
Simulation of the LIVE-J experiments using MELCOR: findings and current limitations 83
Code to code model comparison analysis of Sampson with Melcor for core degradation progression against Fukushima Daiichi NPP UN-1 accident 82
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm 81
Modeling of Multi-Physics Phenomena in Fast Reactors Design/Safety and Experimental Validation 81
Development and Modification of Pool Scrubbing Decontamination Factor Evaluation in Severe Accident Code 81
Molten core relocation analysis of Cora-17 And Cora-18 for the SAMPSON/MCRA validation 80
Numerical analysis of thermally stratified flow in horizontal pipe with upward bend 79
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 3 78
Model uncertainty quantification for fuel rod damage evaluation in SFRs 78
VALIDATION OF SPARC-90 POOL SCRUBBING MODEL IN SEVERE ACCIDENT CODE 77
Radioactive Aerosol Control and Decontamination in the Decommissioning of the Fukushima Daiichi Nuclear Power Station 77
INVESTIGATION ON AEROSOL SPRAY SCAVENGING BY USING A MULTI-HOLE NOZZLE WITH WATER MIST FOR DECOMMISSIONING OF FUKUSHIMA DAIICHI POWER PLANTS 77
EULERIAN TWO-PHASE FLOW MODELING OF STEAM DIRECT CONTACT CONDENSATION FOR THE FUKUSHIMA ACCIDENT INVESTIGATION 76
Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (1) Project Overview and Progress Until 2022 76
The findings obtained during the OECD/NEA BSAF activity with the employment of the Sampson code 75
Numerical investigation of bent pipe flows at transitional Reynolds number 75
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 74
Analysis of accident progression with the SAMPSON code in Fukushima Daiichi nuclear power plant unit 2 73
Benchmark study of the accident at the Fukushima Daiichi NPS: Best-estimate case comparison 73
The Development of a Multiphysics Coupled Solver for Studying the Effect of Dynamic Heterogeneous Configuration on Particulate Debris Bed Criticality and Cooling Characteristics 72
Suppression pool thermal-hydraulics preliminary analysis of fukushima daiichi unit-2 using pool-3D module of Sampson code 72
Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – Overview and first results 72
Analysis of accident progression of Fukushima Dai-ichi with SAMPSON Code - (3) UNIT 3 72
Melt progression analysis of TEPCO's Fukushima Daiichi Unit 3 by the SAMPSON Code 71
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project 70
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 70
Early phase accident progression analysis of Fukushima Daiichi unit 3 by the SAMPSON code 70
Study on general wall damping functions definition: A low reynolds number bounded flows validation 70
Improving accuracy of CFD modelling for direct contact condensation in a suppression pool 69
Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project 68
Eulerian two-phase flow modeling of steam direct contact condensation for the fukushima accident investigation 68
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 68
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2 67
Integral severe accident codes: IMPACT/SAMPSON 67
On the CSAU employment during ULOF accident initiating phase for sodium-cooled fast reactors 66
Preliminary ex-vessel sensitivity study of Fukushima Dai-Ichi unit 1 using DSA1 and CVPA coupling modules of the Sampson Code 66
Revolatilization of iodine by bubbly flow in the suppression pool during an accident 65
State of SAMPSON code development for the analysis of Fukushima Daiichi severe accident 64
Modeling of Rayleigh-Taylor instability for steam direct contact condensation 64
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 64
Validation and application of a new reflooding model for the Sampson Code 62
Three weeks analysis of the Fukushima Daiichi unit 3 NPP by the Sampson code: Contribution to the BSAF-2 project 62
Investigating eutectic behavior and material relocation in B4C-stainless steel composites using the improved MPS method 62
Melting test of penetrating tube through BWR-RPV bottom wall 60
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 60
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 59
Confirmation of severe accident code modeling in light of the findings at Fukushima Daiichi NPPs 59
Three weeks analysis of the Fukushima Daiichi Unit 3 NPP by the SAMPSON code: Contribution to the BSAF-2 project 58
Simulation analysis on accident at Fukushima Daiichi Nuclear Power Plant unit 2 by sampson code 58
PIV Investigation of Jet Mixing Induced by Direct Contact Condensation 57
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 54
Characterization and visualization of eutectic melt in B4C powder and pellet-based/304 stainless steel composite control rods under radiative heating 24
Experimental and numerical analysis of boron diffusion in eutectic melt under uniform radiative heating of B4C-SS control rod composites 23
Totale 8.651
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Categoria #
all - tutte 17.709
article - articoli 8.053
book - libri 0
conference - conferenze 9.518
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 138
Totale 35.418
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2020/202120 0 0 0 0 0 0 0 0 0 0 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
2025/20267.125 873 1.331 715 902 253 598 853 431 508 504 157 0
Totale 8.651