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. A Grand Potential Sintering Model: Derivation and Application to UO2 Thermal Sintering, Doped Sintering, and Irradiation-Enhanced Densification Open Access Author: Greenquist, Ian Title: A Grand Potential Sintering Model: Derivation and Application to UO2 Thermal Sintering, Doped Sintering, and Irradiation-Enhanced Densification Graduate Program: Nuclear Engineering Keywords: Phase fieldSinteringUranium DioxideIrradiation-enhanced densification File: Download Greenquist-Dissertation.pdf Committee Members: Arthur Thompson Motta, Dissertation Advisor/Co-AdvisorArthur Thompson Motta, Committee Chair/Co-ChairKenan Unlu, Committee MemberNick Brown, Committee MemberClive A Randall, Outside Member