1. MESOSCALE SIMULATIONS OF THERMAL TRANSPORT IN W-UO2 CERMET FUEL FOR NUCLEAR THERMAL PROPULSION Open Access Author: Ferreira F Sessim, Marina Title: MESOSCALE SIMULATIONS OF THERMAL TRANSPORT IN W-UO2 CERMET FUEL FOR NUCLEAR THERMAL PROPULSION Graduate Program: Nuclear Engineering Keywords: Nuclear Thermal PropulsionCERMETThermal ConductivityHeat ConductionTungstenUranium DioxideW-UO2Nuclear Fuel File: Download MarinaSessim-Thesis.pdf Committee Members: Michael Tonks, Thesis Advisor/Co-AdvisorArthur Thompson Motta, Committee MemberMary I Frecker, Committee Member
2. DEVELOPMENT OF A PHASE FIELD MODEL OF HYDRIDE MORPHOLOGY IN ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING Open Access Author: Simon, Pierre Clement Title: DEVELOPMENT OF A PHASE FIELD MODEL OF HYDRIDE MORPHOLOGY IN ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING Graduate Program: Nuclear Engineering Keywords: ZirconiumZirconium HydridesPhase Field ModelGrand Potential ModelModelingNuclear MaterialNuclear EngineeringMOOSEVerificationValidationNuclear Fuel Cladding File: Download Simon-MS_thesis.pdf Committee Members: Arthur Thompson Motta, Thesis Advisor/Co-AdvisorMichael R. Tonks, Committee MemberMary I Frecker, Committee Member
