Thesis
- ENEA (CR Bologna, Brasimone, Casaccia e Frascati)
- Idaho National Laboratory (USA)
- ITER
- S.R.S. Servizi di Ricerche e Sviluppo
- Ansaldo Nucleare
- Bangor University
- SCK-CEN
- CEA
- RINA-CSM
Below the title of avaiable thesis:
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Accident analysis for EU-DEMO using MELCOR for FUSION code
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Transient analysis for the ITER WCLL TBM (in collaboration with ENEA Frascati)
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Developing and validation of a fuel expansion module for the PHISICS neutronic code (in collaboration with INL, USA)
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EU-DEMO RELAP5 transient analysis (in collaboration with ENEA CR Brasimone)
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Once Through Steam Generator design and carachterization (in collaboration with ENEA CR Brasimone)
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Preliminary numerical test for the experimental plant STEAM (in collaboration with ENEA CR Brasimone)
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Development of a new computational model to characterize the chemical interaction between tungsten dust and steam in fusion reactors. External implementation in the MELCOR-FUS code and application to LOCA scenarios
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Numerical study of two-phase MHD film flow for liquid metal divertor. Details: 6 - Numerical study of two-phase MHD film flow for liquid metal divertor.pdf
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Development of a computational model to characterize the chemical interaction between tungsten dust and steam/air in fusion reactors. External implementation in the MELCOR-FUS code and application to LOCA/LOFA scenarios. Details: 7 - Development of a computational model to characterize the chemical interaction between tungsten dust and steamair in fusion reactors.pdf
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Fukushima Daichii unit 4 spent fuel pool accident analysis. Details: 8 - Fukushima Daichii unit 4 spent fuel pool accident analysis.pdf
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Application of RELAP5-RAVEN uncertainty methodology on PERSEO experiment. Details: 9 - Application of RELAP5-RAVEN uncertainty methodology on PERSEO experiment.pdf
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Versatile Lead-Loop Facility design. Analysis, performance assessment and conceptualization of the heat removal system (in collaboration with CR ENEA Brasimone)
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ATHENA large lead loop facility. Primary and secondary system coupling, thermal-hydraulic analysis, system behavior by STH code (in collaboration with CR ENEA Brasimone)
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Sviluppo codice di calcolo FEBE per l'analisi meccanica di nocciolo di un reattore veloce (in collaborazione CR ENEA Bologna)
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Sviluppo di un algoritmo di ottimizzazione della strategia di refuelling per reattori veloci (in collaborazione CR ENEA Bologna)
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Innovative BOP system for lead cooled fast reactor. Supercritical CO2 Power Cycles (in collaboration with CR ENEA Brasimone)
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Computational Fluid Dynamic analysis on fuel pin bundle for lead-cooled fast reactor (in collaboration with CR ENEA Brasimone)
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Supporting the Primary Heat Exchanger Experimental Programme (in collaboration with SCK-CEN)
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MACCS consequencies analysis for an unmitigated accident
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Validazione sperimentale di modelli di corrosione per acciai impiegati nell'industria nucleare e simulazione dei prodotti di corrosione attivati in circuiti di refrigerazione di impianti a fusione di tipo tokamak (in collaborazione con RINA-CSM e ENEA Frascati)