Conceptual Design and Preliminary Safety Analysis of a Proposed Nuclear Microreactor for Mobile Application, A. S. M. Fakhrul Islam
Theses and Dissertations

Thermodynamic Assessment of Chromium Corrosion In The Na-K-Mg-U(III, IV) Chloride Salt, Jacob Allen Yingling
Theses and Dissertations

Nuclear Fuel Cycle: Safe Management of Spent Nuclear Fuel, Robert L. Sindelar
Journal of the South Carolina Academy of Science

Mechanistic Multiphysics Modeling of Cladding Rupture in Nuclear Fuel Rods During Loss-Of-Coolant Accident Conditions, Kyle Allan Lawrence Gamble
Theses and Dissertations

Thermal-Hydraulic System Analysis of a Proposed 1 MWth Nuclear Gas Cooled Microreactor, Aaron S. Fernandez
Theses and Dissertations

Experimental Evaluation of Drying Spent Nuclear Fuel for Dry Cask Storage Through Vacuum and Forced Helium Dehydration, Jonathan Ellis Perry
Theses and Dissertations

Computational Modeling of Radiation Damage in a Multi-Phase Ceramic Waste Form Using MOOSE, Zeyu Chen
Theses and Dissertations

Modeling Neutron Interaction Inside a 2D Reactor Using Monte Carlo Method, A. S. M. Fakhrul Islam
Theses and Dissertations

Modeling the Uranium-Silicon Phase Equilibria Based on Computational and Experimental Analysis, Tashiema Lixona Ulrich
Theses and Dissertations

Bison Simulation-Based Identification of Important Design Criteria for U3SI2 Fuels With Composite-Monolithic Duplex Sic Cladding, Jacob A. Yingling
Theses and Dissertations

Characterization and Drying of Oxyhydroxides on Aluminum Clad Spent Nuclear Fuel, Matthew Shalloo
Theses and Dissertations

Implementation of View Factor Model and Radiative Heat Transfer Model in MOOSE, Abdurrahman Ozturk
Theses and Dissertations

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
Theses and Dissertations

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
Theses and Dissertations

Mechanical Characterization and Non-Destructive Evaluation of SiCF-SiCM Composite Tubing with the Impulse Excitation Technique, Nathaniel Truesdale
Theses and Dissertations

Dosimetry, Activation, and Robotic Instrumentation Damage Modeling of the Holtec HI-STORM 100 Spent Nuclear Fuel System, C. Ryan Priest
Theses and Dissertations

Analysis Of Pellet Cladding Interaction And Creep Of U3Si2 Fuel For Use In Light Water Reactors, Kathryn E. Metzger
Theses and Dissertations

Deformation Induced Martensitic Transformation In 304 Stainless Steels, Junliang Liu
Theses and Dissertations

Intercode Advanced Fuels and Cladding Comparison Using BISON, FRAPCON, and FEMAXI Fuel Performance Codes, Aaren Rice
Theses and Dissertations

Experimental Study of Thermo-Mechanical Behavior of SiC Composite Tubing under High Temperature Gradient using Solid Surrogate, Luis Alva, Kirill Shapovalov, George M. Jacobsen, Christina A. Back, Xinyu Huang
Faculty Publications

High Pressure Burst Testing of SiCf-SiCm Composite Nuclear Fuel Cladding, Luis Alva, Xinyu Huang, George M. Jacobsen, Christina A. Back
Faculty Publications

Correlation of Deep Levels With Detector Performance in 4H-SiC Epitaxial Schottky Barrier Alpha Detectors, K. C. Mandal, S. K. Chaudhuri, K. V. Nguyen, M. A. Mannan
Faculty Publications

Large Area Cd_0.9Zn_0.1Te Pixelated Detector: Fabrication and Characterization, S. K. Chaudhuri, K. V. Nguyen, R. O. Pak, L. Matei, V. Buliga, M. Groza, A. Burger, K. C. Mandal
Faculty Publications

System Analysis with Improved Thermo-Mechanical Fuel Rod Models for Modeling Current and Advanced LWR Materials in Accident Scenarios, Ian Edward Porter
Theses and Dissertations

Implementation and Evaluation of Fuel Creep Using Advanced Light-Water Reactor Materials in FRAPCON 3.5, Spencer Carroll
Theses and Dissertations

Novel Thermo-Mechanical Testing Method of Nuclear Fuel Cladding at Elevated Temperature, Luis Alva, Xinyu Huang, Michael A. Sutton, Ning Li
Faculty Publications

Characterization of Two ODS Alloys: 18Cr ODS and 9Cr ODS, Julianne Goddard
Julianne Goddard

Modified Sodium Diuranate Process For the Recovery of Uranium From Uranium Hexafluoride Transport Cylinder Wash Solution, Austin Dean Meredith
Theses and Dissertations

Low Energy X-Ray and ɣ-Ray Detectors Fabricated on n-Type 4H-SiC Epitaxial Layer, K. C. Mandal, P. G. Muzykov, S. K. Chaudhuri, J. R. Terry
Faculty Publications

Cd_0.9Zn_0.1Te Crystal Growth and Fabrication of Large Volume Single-Polarity Charge Sensing Gamma Detectors, S. K. Chaudhuri, Ramesh Madhu Krishna, K. J. Zavalla, L. Matei, V. Buliga, M. Groza, A. Burger, K. C. Mandal
Faculty Publications

Predicting the Crack Response for a Pipe with a Complex Crack, Robert George Lukess
Theses and Dissertations

Evolution of Microstructure of Haynes 230 and Inconel 617 Under Mechanical Testing At High Temperatures, Kyle Hrutkay
Theses and Dissertations

Fabrication and Characterization of Surrogate Fuel Particles Using the Spark Erosion Method, Kathryn Elizabeth Metzger
Theses and Dissertations

The Study of Alternate, Solid-Phase Fluorinating Agents for Use in Reactive Gas Recycle of Used Nuclear Fuel, Dillon Inabinett
Theses and Dissertations

Characterization of Two ODS Alloys: 18Cr ODS and 9Cr ODS, Julianne Kay Goddard
Theses and Dissertations

Pellet Cladding Mechanical Interactions of Ceramic Claddings Fuels Under Light Water Reactor Conditions, Bo-Shiuan Li
Theses and Dissertations

Advanced Fuels Modeling: Evaluating the Steady-State Performance of Carbide Fuel in Helium-Cooled Reactors Using FRAPCON 3.4, Luke H. Hallman
Theses and Dissertations

Characterization of Amorphous Selenium Alloy Detectors for x-rays and High Energy Nuclear Radiation Detection, K. C. Mandal, A. Mehta, S. K. Chaudhuri, Y. Cui, M. Groza, A. Burger
Faculty Publications

Application of Computational Fluid Dynamics Methods to Improve Thermal Hydraulic Code Analysis, Dennis Shannon Sentell, Jr.
Theses and Dissertations

Fabrication and Characterization of High Barrier Cd_0.9Zn_0.1Te Schottky Diodes for High Resolution Nuclear Radiation Detectors, K. C. Mandal, Ramesh Madhu Krishna, P. G. Muzykov, Timothy C. Hayes
Faculty Publications

Characterization of 4H-SiC Epitaxial Layers and High-Resistivity Bulk Crystals for Radiation Detectors, K. C. Mandal, P. G. Muzykov, Ramesh Madhu Krishna, J. R. Terry
Faculty Publications

Neutronic Characteristics of Using Zirconium Diboride and Gadolinium in a Westinghouse 17 X 17 Fuel Assembly, Charlie Sironen
Theses and Dissertations

Performance of Cd_0.9Zn_0.1Te Based High-Energy Gamma Detectors in Various Single Polarity Sensing Device Geometries, S. K. Chaudhuri, Ramesh Madhu Krishna, K. J. Zavalla, L. Matei, V. Buliga, M. Groza, A. Burger, K. C. Mandal
Faculty Publications

Fabrication and Characterization of Cd_0.9Zn_0.1Te Schottky Diodes for Nuclear Radiation Detectors, K. C. Mandal, P. G. Muzykov, Ramesh Madhu Krishna, Timothy C. Hayes
Faculty Publications

Layered GaTe Crystals for Radiation Detectors, K. C. Mandal, Ramesh Madhu Krishna, Timothy C. Hayes, P. G. Muzykov, Sandip Das, Tangali S. Sudarshan, Shuguo Ma
Faculty Publications

Characterization of Semi-Insulating 4H Silicon Carbide for Radiation Detectors, K. C. Mandal, Ramesh Madhu Krishna, P. G. Muzykov, Sandip Das, Tangali S. Sudarshan
Faculty Publications

Fuel Cycle Modeling Improvements and Multi-Tiered Recycling With A Sodium-Cooled Heterogeneous Innovative Burner Reactor, Carey McIlwaine Read Jr.
Theses and Dissertations

The Deposition Characteristics of Zrc On Uo2 Kernels Produced For Advanced Triso Fuels In Gen-Iv Reactors, Ian Edward Porter
Theses and Dissertations

Thermodynamic and Thermochemical Investigation of Advanced Triso Coated Particle Fuels, Seung Min Lee
Theses and Dissertations

Characterization of Radiation Fields and Dose Assessment From Fuels Manufacturing For Advanced Fuel Cycles, Benjamin James Hawkins
Theses and Dissertations

Feasibility Study of Minor Actinide Transmutation In Light-Water Reactors With Various Am/Cm Separation Efficiencies, Daniell Joseph Tincher
Theses and Dissertations

The Effect of Coating Parameters On Advanced TRISO Fuels With Zirconium Carbide, Dennis Franklin Gehr
Theses and Dissertations

Characterization of Uranium Carbide Microspheres In An Inert Zirconium Carbide Matrix For Gas Fast Reactors, Jerome J. Geathers
Theses and Dissertations

Nuclear Fuel Requirements For the American Economy - A Model, Thomas Dexter Curtis
Theses and Dissertations

Analysis of U-Zr-C-O Quaternary System for Applications in Advanced ZRC Coated Triso Particles, Jonathan Lee DeGange
Theses and Dissertations

NaBH 4/H2O2 Fuel Cells for Air Independent Power Systems, Nie Luo, G. H. Miley, Kyu Jung Kim, Rodney Burton, Xinyu Huang
Faculty Publications

Characterization of Low-Defect Cd_0.9Zn_0.1Te and CdTe Crystals for High-Performance Frisch Collar Detectors, K. C. Mandal, S. H. Kang, M. Choi, A. Kargar, M. J. Harrison, D. S. McGregor, A. E. Bolotnikov, G. A. Carini, G. C. Camarda, R. B. James
Faculty Publications