1. FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK Open Access Author: Kern, Ludwig August Title: FLUENT CFD MODELING IN DESIGN OF SPENT NUCLEAR FUEL DRY STORAGE CASK Graduate Program: Nuclear Engineering Keywords: Fluentfluent modelingcfdcfd modelingfluent modelcfd modelcomputational fluid dynamicsnuclearnuclear engineeringdry storagedry storage caskspent fuelspent nuclear fuelnuclear fuelrbmkchernobylholtecthermalheat transfernatural convectionconvectionnatural convective flowannularprototypefull-scalevalidationcfd codenavier-stokesnavier-stokes equation File: Download Kern_MS_NucE_Thesis_2009_FINAL.pdf Committee Members: Fan Bill B Cheung, Thesis Advisor/Co-AdvisorFan Bill B Cheung, Thesis Advisor/Co-AdvisorJohn Michael Cimbala, Thesis Advisor/Co-Advisor
2. Modeling and Design of A New Core-Moderator Assembly and Neutron Beam Ports for the Penn State Breazeale Nuclear Reactor (PSBR) Open Access Author: Ucar, Dundar Title: Modeling and Design of A New Core-Moderator Assembly and Neutron Beam Ports for the Penn State Breazeale Nuclear Reactor (PSBR) Graduate Program: Nuclear Engineering Keywords: PSBRBreazealeTRIGANeutronicThermalHydraulicsMCNPANSYSFluentAnalysisDesignColdNeutronBeam PortCFD File: Download DundarUcar_PhD_Thesis.pdf Committee Members: Kenan Unlu, Dissertation Advisor/Co-AdvisorKenan Unlu, Committee Chair/Co-ChairKostadin Nikolov Ivanov, Committee MemberMaria Nikolova Avramova, Committee MemberThomas Fu Yuan Lin, Committee MemberMahmut Taylan Kandemir, Committee Member
