Thesis

Thesis in Thermoidraulic Area
Several thesis are avaiable in thermoidraulic field, conducted with our research group (headed by Prof. Caruso), sometimes in collaboration with other Universities, companies, research centers such as: 
 
  • 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:

  1. Accident analysis for EU-DEMO using MELCOR for FUSION code

  2. Transient analysis for the ITER WCLL TBM (in collaboration with ENEA Frascati)

  3. Developing and validation of a fuel expansion module for the PHISICS neutronic code (in collaboration with INL, USA)

  4. Preliminary design of a PHRS for ALFRED using RELAP5

  5. EU-DEMO RELAP5 transient analysis (in collaboration with ENEA CR Brasimone)

  6. Once Through Steam Generator design and carachterization (in collaboration with ENEA CR Brasimone)

  7. Preliminary numerical test for the experimental plant STEAM (in collaboration with ENEA CR Brasimone)

  8. 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

  9. 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

  10. 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

  11. Fukushima Daichii unit 4 spent fuel pool accident analysis. Details: 8 - Fukushima Daichii unit 4 spent fuel pool accident analysis.pdf

  12. Application of RELAP5-RAVEN uncertainty methodology on PERSEO experiment. Details: 9 - Application of RELAP5-RAVEN uncertainty methodology on PERSEO experiment.pdf

  13. Versatile Lead-Loop Facility design. Analysis, performance assessment and conceptualization of the heat removal system (in collaboration with CR ENEA Brasimone)

  14. ATHENA large lead loop facility. Primary and secondary system coupling, thermal-hydraulic analysis, system behavior by STH code (in collaboration with CR ENEA Brasimone)

  15. Sviluppo codice di calcolo FEBE per l'analisi meccanica di nocciolo di un reattore veloce (in collaborazione CR ENEA Bologna)

  16. Sviluppo di un algoritmo di ottimizzazione della strategia di refuelling per reattori veloci (in collaborazione CR ENEA Bologna)

  17. Innovative BOP system for lead cooled fast reactor. Supercritical CO2 Power Cycles (in collaboration with CR ENEA Brasimone)

  18. Computational Fluid Dynamic analysis on fuel pin bundle for lead-cooled fast reactor (in collaboration with CR ENEA Brasimone)

  19. Supporting the Primary Heat Exchanger Experimental Programme (in collaboration with SCK-CEN)

  20. MACCS consequencies analysis for an unmitigated accident

  21. 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)