{"id":{"repo_id":"uoit","oai_identifier":"oai:ontariotechu.scholaris.ca:10155/1485"},"canonical_url":"https://search.dev.ndltd.org/etd/uoit/oai:ontariotechu.scholaris.ca:10155/1485","repository":{"repo_id":"uoit","name":"Ontario Institute of Technology","base_url":"https://ontariotechu.scholaris.ca/server/oai/request"},"display":{"title":"Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl","abstract":"The 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.","abstract_html":"The 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.","abstract_has_math":false,"creators":["Breeden, Benjamin A. T."],"institution":"University of Ontario Institute of Technology","degree_name":"Master of Applied Science (MASc)","degree_level":null,"degree_discipline":"Nuclear Engineering","degree_department":null,"school":null,"contributors":[],"advisors":["Piro, Markus"],"committee_chairs":[],"committee_members":[],"year":2022,"date_issued":"2022-07-01","date_published":"2022-07-01","updated_at":"2026-07-24T05:35:22Z","subjects":["Severe accident","MELCOR","Thermochimica","Thermodynamics of advanced fuels – international database","Ionic two-sublattice liquid model"],"languages":["en"],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/10155/1485","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.advisor","label":"Advisor","values":["Piro, Markus"]},{"key":"dc:creator","label":"Author","values":["Breeden, Benjamin A. 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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."]},{"key":"dc:title","label":"Title","values":["Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl"]}]}],"canonical_facts":{"dc:contributor.advisor":["Piro, Markus"],"dc:creator":["Breeden, Benjamin A. T."],"dc:date.accessioned":["2022-08-09T16:27:00Z"],"dc:date.available":["2022-08-09T16:27:00Z"],"dc:date.issued":["2022-07-01"],"dc:description.abstract":["The 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."],"dc:identifier.uri":["https://hdl.handle.net/10155/1485"],"dc:language.iso":["en"],"dc:subject":["Severe accident","MELCOR","Thermochimica","Thermodynamics of advanced fuels – international database","Ionic two-sublattice liquid model"],"dc:title":["Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl"],"dc:type":["Thesis"],"thesis:degree_discipline":["Nuclear Engineering"],"thesis:degree_name":["Master of Applied Science (MASc)"],"thesis:institution_name":["University of Ontario Institute of Technology"]},"updated_at":"2026-07-24T05:35:22Z"}