Tesi di Laurea Magistrale

Sono disponibile numerose Tesi di Laurea Magistrali nell'ambito della termoidraulica svolte con nostro gruppo di ricerca (coordinato dal Prof. Caruso), a volte in collaborazione con altre Università, Aziende o Centri di Ricerca italiani o stranieri, tra cui:

• 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

• Texas A&M University

Si riporta di seguito l'elenco delle Tesi di laurea disponibili:

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. FFTF TH-NK coupled simulations for the IAEA Benchmark

5. Preliminary design of a PHRS for ALFRED using RELAP5

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

7. Once-Through Steam Generator design and characterization (in collaboration with ENEA CR Brasimone)

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

9. 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

10. 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

11. 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

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

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

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

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

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

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

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

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

20. Flow-Induced Vibrations (FIV) in Heavy Liquid Metal Fuel Pin Bundle (in collaboration with CR ENEA Brasimone)

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

22. MACCS consequences analysis for an unmitigated accident

23. 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)

24. Design of an experimental apparatus for the investigation of pool boiling on vertical cylindrical bundle useful for passive decay heat removal system to be used in fission and fusion power plant 

25. Update of CHF correlations in RELAP5 mod3.3 using the Grooneveld 2006 lookup tables

26. Analysis of RELAP5 mod 3.3 water modeling capabilities for the breeding blanket components

27. Water loop facility transient analysis using RELAP5 mod3.3 and first wall mockup preliminary design

28. Design of the OTSG test section for the STEAM facility

29. Analysis of accident-tolerant fuels (ATFs) during a severe accident in a water-cooled SMR (in collaboration with CR ENEA Bologna)

30. In-Vessel Melt Retention analysis in water-cooled SMR using MELCOR  (in collaboration with CR ENEA Bologna)

31. Design optimization of heat exchangers belonging to the EU DEMO fuel cycle OUTL (in collaboration with CR ENEA Frascati)

32. CFD investigation and analysis of a liquid metal target for muon production (in collaboration with CR ENEA Brasimone and CERN)

33. Geometry optimization of a liquid metal target for accelerated particles dumping (in collaboration with CR ENEA Brasimone and CERN)

34. Design of an Energy Storage System for EU-DEMO fusion power plant

35. ITER WCLL WCS/Water loop facility transient analysis using RELAP5 mod3.3 (in collaboration with CR ENEA Brasimone)

36. Advanced Nuclear Safety Evaluation of Liquid Metal Using System level TH computer program  (in collaboration with Ansaldo Nucleare)

37. OECD/NEA Benchmark on PKL experiment Multiple SG U-tube rupture (ISP 52, in collaboration with CR ENEA Brasimone)

38. Thermal-Hydraulic analysis of the TRIGA Mark II reactor pool ( in collaboration with POLIMI)