1. Hydrogen distribution in Zircaloy under a temperature gradient: Modeling, Simulation and Experiments Open Access Author: Courty, Olivier Fabrice Title: Hydrogen distribution in Zircaloy under a temperature gradient: Modeling, Simulation and Experiments Graduate Program: Nuclear Engineering Keywords: NuclearMaterialsCladdingZirconiumHydrogenDiffusionPrecipitationX-RayDiffractionsimulationfinite element File: Download Olivier_Thesis_vf2.pdf Committee Members: Arthur Thompson Motta, Thesis Advisor/Co-Advisor
2. Transmission Electron Microscopy Characterization of Zircaloy-4 Subjected to Ion Irradiation Open Access Author: Bowman, Joshua Samuel Title: Transmission Electron Microscopy Characterization of Zircaloy-4 Subjected to Ion Irradiation Graduate Program: Nuclear Engineering Keywords: ZircaloyZirconiumIrradiationIonCladdingCorrosionProtonMUZICTEMPrecipitateAmorphous File: Download Bowman_Thesis_Final.pdf Committee Members: Arthur Thompson Motta, Thesis Advisor/Co-AdvisorXing Wang, Committee MemberJean Paul Allain, Program Head/Chair
3. Hydrogen migration and mechanical behavior of hydrided zirconium alloys Restricted (Penn State Only) Author: Kang, Soyoung Title: Hydrogen migration and mechanical behavior of hydrided zirconium alloys Graduate Program: Nuclear Engineering Keywords: Zirconium hydridehydrogen migrationCladdingMechanical behaviorRing compression TestZirconium alloyDuctility of zirconium alloy File: Login to Download Committee Members: Arthur Motta, Professor in Charge/Director of Graduate StudiesXing Wang, Major Field MemberArthur Motta, Chair & Dissertation AdvisorAllison Beese, Outside Unit & Field MemberMia Jin, Major Field MemberMichael Billone, Special Member