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dc.contributor.advisorPiro, Markus
dc.contributor.authorBreeden, Benjamin A. T.
dc.date.accessioned2022-08-09T16:27:00Z
dc.date.available2022-08-09T16:27:00Z
dc.date.issued2022-07-01
dc.identifier.urihttps://hdl.handle.net/10155/1485
dc.description.abstractThe primary goal of this work was to enhance MELCOR’s material modelling capabilities via one-way coupling of Thermochimica. MELCOR is a state-of-the-art code used to simulate the severe accident progression of a nuclear power plant. The first objective was developing the capabilities in Thermochimica to handle the Ionic Two-sublattice Liquid Model in order to leverage the Thermodynamics of Advanced Fuels – International Database (TAF-ID). Using empirically derived data from the TAF-ID allowed Thermochimica to reliably predict the stable phases of nuclear materials and their composition. Secondly, two test case scenarios were simulated in MELCOR using a generic boiling water reactor design that included Case I: Zircaloy-2 cladding, and Case II: FeCrAl cladding. The results from these two cases were analyzed using a one-way coupling approach with Thermochimica to demonstrate potential areas for the improvement o fMELCOR’s current material modelling capabilities.en
dc.description.sponsorshipUniversity of Ontario Institute of Technologyen
dc.language.isoenen
dc.subjectSevere accidenten
dc.subjectMELCORen
dc.subjectThermochimicaen
dc.subjectThermodynamics of advanced fuels – international databaseen
dc.subjectIonic two-sublattice liquid modelen
dc.titleUsing MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAlen
dc.typeThesisen
dc.degree.levelMaster of Applied Science (MASc)en
dc.degree.disciplineNuclear Engineeringen


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