Author

A. Alemberti

Observed names: A Alemberti, ALEMBERTI Alessandro, Alemberti, A., Alemberti, Alessandro, Alessandro ALEMBERTI, Alessandro Alemberti

Institution: Ansaldo (Italy)

Observed institution: Ansaldo (Italy)

ORCID: 0000-0001-9264-4222

Observed ORCID: 0000-0001-9264-4222

OpenAlex ID: A5071932860

Overview of lead-cooled fast reactor activities

2013 · Alessandro Alemberti, Valery Smirnov, et al. · Progress in Nuclear Energy · 369

European lead fast reactor—ELSY

2011 · Alessandro Alemberti, Johan Carlsson, et al. · Nuclear Engineering and Design · 158

The Lead Fast Reactor: An Opportunity for the Future?

2016 · Alessandro Alemberti · Engineering · 89

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ALFRED reactor coolant system design

2020 · Alessandro Alemberti, Marco Caramello, et al. · Nuclear Engineering and Design · 77

A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly

2014 · Ivan Di Piazza, Fabrizio Magugliani, et al. · Nuclear Engineering and Design · 69

The Lead Fast Reactor: Demonstrator (ALFRED) and ELFR Design

2013 · A. Alemberti, M Frogheri · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 54

Investigations on the phenomenology of ex-vessel core melt behaviour (COMAS)

2001 · W Steinwarz, A Alemberti, et al. · Nuclear Engineering and Design · 34

ELSY—European LFR Activities

2011 · Alessandro ALEMBERTI, Johan CARLSSON, et al. · Journal of Nuclear Science and Technology · 30

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ALFRED: A revised concept to improve pool related thermal-hydraulics

2019 · Michele Frignani, Alessandro Alemberti, et al. · Nuclear Engineering and Design · 29

Pool CFD modelling: lessons from the SESAME project

2019 · V. Moreau, M. Profir, et al. · Nuclear Engineering and Design · 29

The SPES3 Experimental Facility Design for the IRIS Reactor Simulation

2009 · Mario Carelli, Lawrence Conway, et al. · Science and Technology of Nuclear Installations · 29

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Thermal hydraulic analysis of a passively controlled DHR system

2017 · M. Caramello, M. Gregorini, et al. · Progress in Nuclear Energy · 26

AP1000 passive core cooling system pre-operational tests procedure definition and simulation by means of Relap5 Mod. 3.3 computer code

2012 · D. Lioce, M. Asztalos, et al. · Nuclear Engineering and Design · 22

Lead Cooled Fast Reactors

2020 · Alessandro Alemberti · Elsevier eBooks · 18

Material Performance in Lead and Lead-Bismuth Alloy

2015 · Serena Bassini, Sebastiano Cataldo, et al. · Elsevier eBooks · 15

SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases

2018 · R. Marinari, M. Tarantino, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 9

Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors

2017 · Walter Borreani, Alessandro Alemberti, et al. · Energies · 9

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Assessment of the enhanced DHRS configuration for MYRRHA reactor

2016 · E. Bubelis, W. Jaeger, et al. · Nuclear Engineering and Design · 9

Testing and Qualification of CIRCE Venturi-Nozzle Flow Meter for Large Scale Experiments

2005 · P. Agostini, A. Alemberti, et al. · CINECA IRIS Institutial research information system (University of Pisa) · 8

Design of a Decay Heat Removal System for EFIT Plant

2009 · Barbara Leoncini, Alessandro Alemberti, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 5

ELSY - The European Lead Fast Reactor

2009 · ALEMBERTI Alessandro, CARLSSON Johan, et al. · Joint Research Centre (European Commission) · 5

Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor

2020 · Francesco Di Lecce, Manuele Aufiero, et al. · The European Physical Journal Plus · 4

CFD Simulation of X-Ads Downcomer Thermal Stratification

2006 · Anissimov, V., Alemberti, A. · arXiv (Cornell University) · 4

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CFD Pre-Test Analysis and Design of the NACIE-UP BFPS Fuel Pin Bundle Simulator

2016 · R. Marinari, I. Di Piazza, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 3

Theory, design and CFD analysis of a multi-blade screw pump evolving liquid lead for a GEN-IV LFR Nuclear Power Plant

2015 · A. Alemberti, Fabrizio Magugliani, et al. · CINECA IRIS Institutial Research Information System (University of Genoa)

Works count: 36

Citation count: 1,106

H-index: 15

I10-index: 15