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

PELLEGRINI, MARCO
 Distribuzione geografica
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Continente #
AS - Asia 3.666
NA - Nord America 2.717
EU - Europa 2.305
SA - Sud America 577
Continente sconosciuto - Info sul continente non disponibili 127
AF - Africa 81
OC - Oceania 1
Totale 9.474
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Nazione #
US - Stati Uniti d'America 2.588
CN - Cina 1.365
RU - Federazione Russa 1.259
SG - Singapore 1.006
IT - Italia 593
BR - Brasile 468
VN - Vietnam 362
JP - Giappone 318
KR - Corea 287
FR - Francia 110
HK - Hong Kong 87
DE - Germania 82
CA - Canada 68
AR - Argentina 51
GB - Regno Unito 45
IN - India 44
FI - Finlandia 39
CI - Costa d'Avorio 35
NL - Olanda 34
MX - Messico 33
ID - Indonesia 32
BD - Bangladesh 27
SE - Svezia 23
UA - Ucraina 23
EC - Ecuador 22
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 12
CL - Cile 9
PY - Paraguay 9
CO - Colombia 8
IR - Iran 8
MA - Marocco 8
CH - Svizzera 7
SA - Arabia Saudita 7
CR - Costa Rica 6
JM - Giamaica 6
MY - Malesia 6
PH - Filippine 6
NI - Nicaragua 5
RO - Romania 5
SN - Senegal 5
TH - Thailandia 5
UY - Uruguay 5
AZ - Azerbaigian 4
DK - Danimarca 4
KZ - Kazakistan 4
NP - Nepal 4
UZ - Uzbekistan 4
AE - Emirati Arabi Uniti 3
AL - Albania 3
CZ - Repubblica Ceca 3
DO - Repubblica Dominicana 3
EG - Egitto 3
GT - Guatemala 3
KE - Kenya 3
OM - Oman 3
PS - Palestinian Territory 3
TN - Tunisia 3
DZ - Algeria 2
EE - Estonia 2
EU - Europa 2
GR - Grecia 2
LT - Lituania 2
NG - Nigeria 2
PT - Portogallo 2
SV - El Salvador 2
SY - Repubblica araba siriana 2
TJ - Tagikistan 2
VE - Venezuela 2
AM - Armenia 1
BE - Belgio 1
BH - Bahrain 1
BO - Bolivia 1
BW - Botswana 1
CG - Congo 1
CM - Camerun 1
CW - ???statistics.table.value.countryCode.CW??? 1
ET - Etiopia 1
GA - Gabon 1
GF - Guiana Francese 1
HN - Honduras 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
Totale 9.343
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Città #
Singapore 650
Hefei 507
San Jose 467
Ashburn 379
Milan 322
Seoul 266
Tokyo 265
Moscow 172
Ho Chi Minh City 130
Beijing 110
North Charleston 107
Santa Clara 82
Lauterbourg 81
Hanoi 76
Hong Kong 74
Kent 70
Dallas 68
Los Angeles 67
Chandler 66
Las Vegas 59
Council Bluffs 58
Boardman 46
Frisco 45
Rome 44
Ann Arbor 36
Shanghai 35
Frankfurt am Main 33
São Paulo 33
Abidjan 32
Buffalo 32
The Dalles 32
Hangzhou 31
Houston 29
Redondo Beach 28
Atlanta 25
Woodbridge 25
Fairfield 24
New York 24
Turin 23
Sacramento 22
Helsinki 21
Guangzhou 18
Mexico City 18
Wilmington 18
Wuhan 18
Haiphong 17
Karlsruhe 17
Salt Lake City 16
Seattle 16
Zhengzhou 16
Genoa 15
Harbin 15
Shijiazhuang 15
Changsha 14
Chicago 14
Dublin 14
Orem 14
Cambridge 13
Chengdu 13
Chennai 13
Rio de Janeiro 13
Brasília 12
Dearborn 12
Ottawa 12
Toronto 12
Amman 11
Belo Horizonte 11
Montreal 11
Tianjin 11
Warsaw 11
Baghdad 10
Brooklyn 10
Curitiba 10
Denver 10
Lawrence 10
Medford 10
Naples 10
Biên Hòa 9
Porto Alegre 9
Vienna 9
Albuquerque 8
Amsterdam 8
Boston 8
Buenos Aires 8
Da Nang 8
Jakarta 8
London 8
Miami 8
Shenzhen 8
São José dos Campos 8
Taipei 8
Campinas 7
Jacksonville 7
Meridian 7
Mountain View 7
Nuremberg 7
Phoenix 7
Pisa 7
Quito 7
Redwood City 7
Totale 5.354
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Nome #
Validation of the SAMPSON/MCRA Code against CORA-18 Experiment 295
Acknowledgement to reviewers of fluids in 2018 252
Modelling of Multi-Physics Phenomena in Fast Reactor Design: Safety and Experimental Validation 211
Preliminary Considerations from the 2nd Phase of Experiments at the SIET/SWAM Facility 210
Suppression pool testing at the SIET labs (2) Steam chugging investigation under the presence of non-condensable gas in a vertical opened pipe 195
Direct contact condensation experiments for clarification of S/C temperature evolution during long term steam discharge 194
Suppression pool testing at the SIET laboratory (1) Experimental Investigation of Critical Phenomena Expected in the Fukushima Daiichi Suppression Chamber 188
Suppression pool testing at the SIET labs (3) Experiments on Steam Direct Contact Condensation in a Vertical Multi-holes Sparger 173
Suppression pool testing at the SIET laboratory: experimental investigation of critical phenomena expected in the Fukushima Daiichi suppression chamber 171
Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1 145
Investigation of jet induced by direct contact condensation using PIV 143
CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined 138
Transient behaviour and heat transfer characteristics in debris beds: Simulation and analysis of the LIVEJ2 experiment 131
Validation and application of numerical modeling for in-vessel melt retention in corium pools 118
UNSTEADY CFD ANALYSIS OF PARALLEL JET MIXING AS A SUPPORT OF THE IRIS STEAM GENERATOR OUTLET DESIGN 117
Extended development of a bubble percolation method to predict boiling crisis of flow boiling 113
Analysis of accident progression of Fukushima Daiichi NPP by the sampson code 112
Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method 111
Main Outputs from the OECD/NEA ARC-F Project 110
Analysis of the Long Term Interaction Between Molten Core And Dry Concrete At Fukushima Daiichi Unit 1 110
Analysis of melt progression and debris cooling at the Fukushima Daiichi unit 3 by the Sampson Code 109
Study on the difference between B4C powder and B4C pellet regarding the eutectic reaction with stainless steel 108
Analysis of accident progression of Fukushima Daiichi NPPS with Sampson code 107
Radiation Heating Effects on B4C-SS Eutectic Melting and Its Relocation Behaviour 103
An approach toward evaluation of long-term fission product distributions in the Fukushima Daiichi nuclear power plant after the severe accident 102
Algebraic turbulent heat flux model for prediction of thermal stratification in piping systems 102
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 102
An approach toward evaluation of fp behavior in npps under severe accidents 102
A quantitative method of eutectic reaction study between boron carbide and stainless steel 100
Benchmark study of the accident at the fukushima daiichi NPS best estimate case comparison 99
Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere 99
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 98
Eutectic melting and relocation behavior of B4C pellet-stainless steel under radiative heating 98
Thermophoretic Particle Deposition: A Computational Fluid Dynamics Approach for Estimating Hotspots 98
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project 97
A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics 96
Development and Modification of Pool Scrubbing Decontamination Factor Evaluation in Severe Accident Code 96
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 3 95
A numerical study on turbulence attenuation model for liquid droplet impingement erosion 95
Code to code model comparison analysis of Sampson with Melcor for core degradation progression against Fukushima Daiichi NPP UN-1 accident 94
Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections 94
Prediction of thermal stratification in a u-bent pipe: A URANS validation 93
Accident analysis of Fukushima Daiichi nuclear power plant unit 2 by the SAMPSON severe accident code 92
Visualization Experiments of Radiation Heating on the Eutectic Reaction Between B4C-SS and Its Relocation Behavior 91
Simulation of the LIVE-J experiments using MELCOR: findings and current limitations 91
Accident analysis of Fukushima Daiichi nuclear power plant unit 1 by the sampson severeaccidentcode 90
On the interaction of boundary layer and mixing layer in stratified pipe flow 89
Analysis of accident progression with the SAMPSON code in Fukushima Daiichi nuclear power plant unit 2 88
Numerical Simulation and Validation of Debris Bed Self-Leveling Behavior with Mixed-Density Particles Using CFD-DEM Coupling Algorithm 87
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 87
The findings obtained during the OECD/NEA BSAF activity with the employment of the Sampson code 84
Study on Eutectic Melting Behavior of Control Rod Materials in Severe Accidents of Sodium-Cooled Fast Reactors (1) Project Overview and Progress Until 2022 84
INVESTIGATION ON AEROSOL SPRAY SCAVENGING BY USING A MULTI-HOLE NOZZLE WITH WATER MIST FOR DECOMMISSIONING OF FUKUSHIMA DAIICHI POWER PLANTS 84
Radioactive Aerosol Control and Decontamination in the Decommissioning of the Fukushima Daiichi Nuclear Power Station 83
Benchmark study of the accident at the Fukushima Daiichi NPS: Best-estimate case comparison 83
EULERIAN TWO-PHASE FLOW MODELING OF STEAM DIRECT CONTACT CONDENSATION FOR THE FUKUSHIMA ACCIDENT INVESTIGATION 82
Numerical analysis of thermally stratified flow in horizontal pipe with upward bend 82
Modeling of Multi-Physics Phenomena in Fast Reactors Design/Safety and Experimental Validation 82
VALIDATION OF SPARC-90 POOL SCRUBBING MODEL IN SEVERE ACCIDENT CODE 81
Model uncertainty quantification for fuel rod damage evaluation in SFRs 81
Eulerian two-phase flow modeling of steam direct contact condensation for the fukushima accident investigation 81
Molten core relocation analysis of Cora-17 And Cora-18 for the SAMPSON/MCRA validation 81
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 80
The Development of a Multiphysics Coupled Solver for Studying the Effect of Dynamic Heterogeneous Configuration on Particulate Debris Bed Criticality and Cooling Characteristics 80
Numerical investigation of bent pipe flows at transitional Reynolds number 79
Melt progression analysis of TEPCO's Fukushima Daiichi Unit 3 by the SAMPSON Code 79
Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2 79
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project 78
Integration of pool scrubbing research to enhance Source-Term calculations (IPRESCA) project – Overview and first results 78
Analysis of accident progression of Fukushima Dai-ichi with SAMPSON Code - (3) UNIT 3 76
Improving accuracy of CFD modelling for direct contact condensation in a suppression pool 75
On the CSAU employment during ULOF accident initiating phase for sodium-cooled fast reactors 75
Early phase accident progression analysis of Fukushima Daiichi unit 3 by the SAMPSON code 75
State of SAMPSON code development for the analysis of Fukushima Daiichi severe accident 74
Suppression pool thermal-hydraulics preliminary analysis of fukushima daiichi unit-2 using pool-3D module of Sampson code 74
Integral severe accident codes: IMPACT/SAMPSON 74
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 74
Revolatilization of iodine by bubbly flow in the suppression pool during an accident 72
Modeling of Rayleigh-Taylor instability for steam direct contact condensation 72
Study on general wall damping functions definition: A low reynolds number bounded flows validation 72
Preliminary ex-vessel sensitivity study of Fukushima Dai-Ichi unit 1 using DSA1 and CVPA coupling modules of the Sampson Code 72
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 71
Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project 69
PIV Investigation of Jet Mixing Induced by Direct Contact Condensation 69
Validation and application of a new reflooding model for the Sampson Code 67
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 66
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 66
Investigating eutectic behavior and material relocation in B4C-stainless steel composites using the improved MPS method 65
Melting test of penetrating tube through BWR-RPV bottom wall 64
Three weeks analysis of the Fukushima Daiichi unit 3 NPP by the Sampson code: Contribution to the BSAF-2 project 63
Confirmation of severe accident code modeling in light of the findings at Fukushima Daiichi NPPs 62
Simulation analysis on accident at Fukushima Daiichi Nuclear Power Plant unit 2 by sampson code 62
Three weeks analysis of the Fukushima Daiichi Unit 3 NPP by the SAMPSON code: Contribution to the BSAF-2 project 61
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 57
Experimental and numerical analysis of boron diffusion in eutectic melt under uniform radiative heating of B4C-SS control rod composites 35
Characterization and visualization of eutectic melt in B4C powder and pellet-based/304 stainless steel composite control rods under radiative heating 32
Totale 9.474
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Categoria #
all - tutte 20.598
article - articoli 9.500
book - libri 0
conference - conferenze 10.938
curatela - curatele 0
other - altro 0
patent - brevetti 0
selected - selezionate 0
volume - volumi 160
Totale 41.196
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Totale Lug Ago Sett Ott Nov Dic Gen Feb Mar Apr Mag Giu
2021/202285 0 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
2025/20267.657 873 1.331 715 902 253 598 853 431 508 504 193 496
2026/2027291 261 30 0 0 0 0 0 0 0 0 0 0
Totale 9.474