Theses/Dissertations from 2023
Conceptual Design and Preliminary Safety Analysis of a Proposed Nuclear Microreactor for Mobile Application, A. S. M. Fakhrul Islam
Theses/Dissertations from 2022
Thermal-Hydraulic System Analysis of a Proposed 1 MWth Nuclear Gas Cooled Microreactor, Aaron S. Fernandez
Mechanistic Multiphysics Modeling of Cladding Rupture in Nuclear Fuel Rods During Loss-Of-Coolant Accident Conditions, Kyle Allan Lawrence Gamble
Thermodynamic Assessment of Chromium Corrosion In The Na-K-Mg-U(III, IV) Chloride Salt, Jacob Allen Yingling
Theses/Dissertations from 2021
Experimental Evaluation of Drying Spent Nuclear Fuel for Dry Cask Storage Through Vacuum and Forced Helium Dehydration, Jonathan Ellis Perry
Theses/Dissertations from 2020
Computational Modeling of Radiation Damage in a Multi-Phase Ceramic Waste Form Using MOOSE, Zeyu Chen
Theses/Dissertations from 2019
Modeling Neutron Interaction Inside a 2D Reactor Using Monte Carlo Method, A. S. M. Fakhrul Islam
Implementation of View Factor Model and Radiative Heat Transfer Model in MOOSE, Abdurrahman Ozturk
Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel, Matthew Shalloo
Modeling the Uranium-Silicon Phase Equilibria Based on Computational and Experimental Analysis, Tashiema Lixona Ulrich
Modeling complex oxides: Thermochemical behavior of nepheline-forming Na-Al-Si-B-K-Li-Ca-Mg-Fe-O and hollandite-forming Ba-Cs-Ti-Cr-Al-Fe- Ga-O systems, Stephen A. Utlak
Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding, Jacob A. Yingling
Theses/Dissertations from 2017
Mechanical Characterization and Non-Destructive Evaluation of SiCF-SiCM Composite Tubing with the Impulse Excitation Technique, Nathaniel Truesdale
Theses/Dissertations from 2016
Deformation Induced Martensitic Transformation In 304 Stainless Steels, Junliang Liu
Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors, Kathryn E. Metzger
Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System, C. Ryan Priest
Theses/Dissertations from 2015
Intercode Advanced Fuels and Cladding Comparison Using BISON, FRAPCON, and FEMAXI Fuel Performance Codes, Aaren Rice
Theses/Dissertations from 2014
Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5, Spencer Carroll
System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios, Ian Edward Porter
Theses/Dissertations from 2013
Characterization of Two ODS Alloys: 18Cr ODS and 9Cr ODS, Julianne Kay Goddard
Advanced Fuels Modeling: Evaluating the Steady-State Performance of Carbide Fuel in Helium-Cooled Reactors Using FRAPCON 3.4, Luke H. Hallman
Evolution of Microstructure of Haynes 230 and Inconel 617 Under Mechanical Testing At High Temperatures, Kyle Hrutkay
The Study of Alternate, Solid-Phase Fluorinating Agents for Use in Reactive Gas Recycle of Used Nuclear Fuel, Dillon Inabinett
Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions, Bo-Shiuan Li
Predicting the Crack Response for a Pipe with a Complex Crack, Robert George Lukess
Modified Sodium Diuranate Process For the Recovery of Uranium From Uranium Hexafluoride Transport Cylinder Wash Solution, Austin Dean Meredith
Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method, Kathryn Elizabeth Metzger
Application of Computational Fluid Dynamics Methods to Improve Thermal Hydraulic Code Analysis, Dennis Shannon Sentell, Jr.
Theses/Dissertations from 2012
Neutronic Characteristics of Using Zirconium Diboride and Gadolinium in a Westinghouse 17 X 17 Fuel Assembly, Charlie Sironen
Theses/Dissertations from 2011
Thermodynamic and Thermochemical Investigation of Advanced Triso Coated Particle Fuels, Seung Min Lee
The Deposition Characteristics of Zrc On Uo2 Kernels Produced For Advanced Triso Fuels In Gen-Iv Reactors, Ian Edward Porter
Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor, Carey McIlwaine Read Jr.
Theses/Dissertations from 2010
Characterization of Radiation Fields and Dose Assessment From Fuels Manufacturing For Advanced Fuel Cycles, Benjamin James Hawkins
Feasibility Study of Minor Actinide Transmutation In Light-Water Reactors With Various Am/Cm Separation Efficiencies, Daniell Joseph Tincher
Theses/Dissertations from 2009
Nuclear Fuel Requirements For the American Economy - A Model, Thomas Dexter Curtis
Analysis of U-Zr-C-O Quaternary System for Applications in Advanced ZRC Coated Triso Particles, Jonathan Lee DeGange
Characterization of Uranium Carbide Microspheres In An Inert Zirconium Carbide Matrix For Gas Fast Reactors, Jerome J. Geathers
The Effect of Coating Parameters On Advanced TRISO Fuels With Zirconium Carbide, Dennis Franklin Gehr