# positions[].organizations[].parent[].label
Texas A&M Engineering Experiment Station (TEES)

# positions[].organizations[].parent[].label
Texas A&M Engineering Experiment Station (TEES)

# positions[].organizations[].parent[].label
Texas A&M Engineering Experiment Station (TEES)

# keywords[]
High-burnup Simplified Boiling Water Reactor

# keywords[]
16 Peace, Justice And Strong Institutions

# keywords[]
Zirconium And Hafnium Carbide Substrates

# keywords[]
12 Responsible Consumption And Production

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
Physical Injury - Accidents And Adverse Effects

# educationAndTraining[].organization.label
Purdue University - (West Lafayette, Indiana, United States)

# educationAndTraining[].organization.label
Purdue University - (West Lafayette, Indiana, United States)

# educationAndTraining[].organization.label
Purdue University - (West Lafayette, Indiana, United States)

# publications[].label
Separate-Effects Validation Experiments for Models of Fracture in Ceramic Nuclear Fuel

# publications[].label
ELECTRODE MATERIALS FOR THE REDUCTION OF CAO AND LI2O FOR ACTINIDE PYROPROCESSING

# publications[].label
Interfacial Reactions Between Metals and Ceramics at Elevated Temperatures

# publications[].label
Thermal-shock experiments for separate-effects validation of UO₂ fuel fracture models

# publications[].label
Decomposition of the  phase in as-cast and quenched U-Zr alloys

# publications[].label
Hydride Formation Process for the Powder Metallurgical Recycle of Zircaloy from Used Nuclear Fuel

# publications[].label
TAMU Nuclear safety curriculum development for a 21stcentury workforce

# publications[].label
Laves inter-metallics in stainless steel-zirconium alloys

# publications[].label
Ascertaining directionality information from incident nuclear radiation

# publications[].label
Detecting the Oxidation of Zircaloy Claddings by Infrared Interference

# publications[].label
EIS monitoring of electrochemical behavior of 304L stainless steel during immersion in a diluted nitric acid solution

# publications[].label
Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR

# publications[].label
Potential zircaloy recycle method via hydride formation

# publications[].label
Interface Interactions of Dissimilar Materials at Elevated Temperatures

# publications[].label
Removal of Lithium Antimonide from Radioactive Glove Box

# publications[].publisher
American Society of Civil Engineers (ASCE)

# publications[].label
Real-time detection of UREX+3a extraction streams for process monitoring applications

# publications[].label
TENSION METASTABLE FLUID DETECTION SYSTEMS FOR SPECIAL NUCLEAR MATERIAL DETECTION AND MONITORING

# publications[].label
Manufacture of a UO₂-Based Nuclear Fuel with Improved Thermal Conductivity with the Addition of BeO

# publications[].label
Synthesis and casting of a lithium-bismuth compound for an ion-replacement electrorefiner

# publications[].label
Hydride formation process development for the powder metallurgical recycle of zircaloy

# publications[].label
Interfacial reactions of zirconium and zirconium-alloy liquid metals with beryllia at elevated temperatures

# publications[].label
Development of experimental capabilities for fuels and materials testing in the versatile test reactor

# publications[].label
Behavior assessments for UO<inf>2</inf>-BEO enhanced conductivity fuel in a PWR

# publications[].label
Evaluation of stainless steel zirconium alloys as high-level nuclear waste forms

# publications[].label
Real-time monitoring of actinides in chemical nuclear fuel reprocessing plants

# publications[].tags
16 Peace, Justice and Strong Institutions

# publications[].label
UREX+ centrifugal contactor corrosion in HNO<inf>3</inf>-HF aqueous solutions

# publications[].label
Development of a high density uranium nitride-uranium silicide composite accident tolerant fuel

# publications[].label
The effect of actinides on the microstructural development in a metallic high-level nuclear waste form

# publications[].label
Experimentally validated multiphysics modeling of fracture induced by thermal shocks in sintered UO2 pellets

# publications[].label
Uranium processing for the nuclear fuel cycle

# publications[].label
Corrosion Behavior of AISI 304L Stainless Steel for Applications in Nuclear Waste Reprocessing Equipment

# publications[].label
A novel method for the design and selection of neutron-attenuating media

# publications[].label
Laboratory-based 3D X-ray microscopy of unirradiated U-10Zr fuel

# publications[].label
Thoria-Based Cermet Nuclear Fuel: Sintered Microsphere Fabrication by Spray Drying

# publications[].label
Design and Demonstration of a Rabbit Experiment System for the Versatile Test Reactor

# publications[].label
Zirconium matrix cermet storage form and transmutation fuel for transuranics

# publications[].label
Microstructure of -U and -UZr₂ phase uranium-zirconium alloys irradiated with 140-keV He+ ion-beam

# publications[].label
Microscopy and neutron diffraction study of a zirconium-8 wt% stainless steel alloy

# publications[].label
Powder metallurgy of alpha phase uranium alloys for TRU burning fast reactors

# publications[].label
The role of interfaces in ceramic-metal bonding

# publications[].label
Effect of hydrogen concentration on neutron moderation of hydrides at 900 K

# publications[].label
Phase development in As-cast, zirconium-based alloys containing type 304 stainless steel and Pu

# publications[].label
Development of a real-time detection strategy for process monitoring during nuclear fuel reprocessing using the UREX+3a method

# publications[].label
Characterization of high strength alloy formed by ion irradiation of metallic glasses

# publications[].label
The development of stable ceramic materials for the containment of molten zirconium and uranium alloys

# publications[].label
Concept Descriptions for the VTR Rabbit System and Driver Fuel Test Assemblies

# publications[].label
Monitoring and Predicting Stress Corrosion Cracking of Long Term Spent Nuclear Fuel Storage

# publications[].publisher
Association for Materials Protection and Performance (AMPP)

# publications[].label
Nuclear fuel and method of fabricating the same

# publications[].label
Corrosion Behavior of Type 304L Stainless Steel in UREX plus Nitric Acid Solutions Using Immersion and Rotating Cage Techniques

# publications[].publisher
Association for Materials Protection and Performance (AMPP)

# publications[].label
Powder metallurgical fabrication of zirconium matrix cermet nuclear fuels

# publications[].label
Thermophysical investigations of the uranium-zirconium alloy system

# publications[].label
Isolating wastes in the electrometallurgical treatment of spent nuclear fuel

# publications[].label
ICONE11-36576 STAR-H2 : A 400 MWTH LEAD-COOLED, LONG REFUELING INTERVAL REACTOR FOR HYDROGEN PRODUCTION

# publications[].label
Pollucite and feldspar formation in sintered bentonite for nuclear waste immobilization

# publications[].label
Experimentally Validated Multiphysics Modeling of Fracture Induced by Thermal Shocks in Sintered UO2 Pellets

# publications[].label
Performance of structural materials in lead-based reactor coolants at temperatures up to 800C

# publications[].label
Coexistence of the  and  phases in an as-cast uranium-rich UZr alloy

# publications[].label
Real-time detection of UREX + 3a extraction streams for materials accountancy

# publications[].label
Fabrication of ZrN Barrier Coatings for U-Mo Microspheres Via Fluidized Bed Chemical Vapor Deposition Using a Metalorganic Precursor

# publications[].label
An experimentally validated mesoscale model for the effective thermal conductivity of U-Zr fuels

# publications[].label
Influence of zirconium content on fission product distributions in stainless steel zirconium waste forms.

# publications[].label
Alloy development for advanced inert-matrix nuclear fuels

# publications[].label
Waste forms from the electrometallurgical treatment of DOE spent fuel: Production and general characteristics

# publications[].label
3D printing high temperature materials for nuclear industry applications

# publications[].label
Corrosion testing of stainless steel-zirconium metal waste forms

# publications[].tags
12 Responsible Consumption and Production

# publications[].label
Cermet fuels for advanced fuel cycles and transmutation

# publications[].label
Improved leach resistance of FLiBe by conversion to a substituted fluorapatite

# publications[].label
Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design

# publications[].label
Introducing a high thermal conductivity UO<inf>2</inf>-BeO nuclear fuel concept

# publications[].label
Thermal conductivity of uranium metal and uranium-zirconium alloys fabricated via powder metallurgy

# publications[].label
Hot-isostatic pressing of U-1OZr by a coupled grain boundary diffusion and creep cavitation mechanism

# publications[].label
PREPARATION AND PERFORMANCE OF U-10ZR ALLOY NUCLEAR-FUEL USING POWDER-METALLURGY TECHNIQUES

# publications[].label
An Experimentally Validated Mesoscale Model of Thermal Conductivity of a UO2 and BeO Composite Nuclear Fuel

# publications[].label
UREX+ 304L stainless steel centrifugal contactor corrosion due to hydrodynamic effects

# publications[].label
Anisotropic Radiation-Induced Changes in Type 316L Stainless Steel Rods Built by Laser Additive Manufacturing

# publications[].label
Sample preparation of U-Zr fuel alloys for TEM analysis

# publications[].label
Ion irradiation induced nanocrystal formation in amorphous Zr₅₅Cu₃₀Al₁₀Ni₅ alloy

# publications[].label
Background studies for the MINER Coherent Neutrino Scattering reactor experiment

# publications[].label
Evaluation of zirconium-iron-rhenium alloy surrogates for a technetium alloy waste form

# publications[].label
Texture evolution during annealing of hot extruded U-10wt%Zr alloy by in situ neutron diffraction

# publications[].label
Thoria-Based Cermet Nuclear Fuel: Neutronics Fuel Design and Fuel Cycle Analysis

# publications[].label
Assessing Corrosion of UNS S30403 Stainless Steel for Applications in Nuclear Waste Reprocessing Systems

# publications[].publisher
Association for Materials Protection and Performance (AMPP)

# publications[].label
Evaluation of high thermal conductivity oxide nuclear fuel concept containing beryllium

# publications[].label
Microstructure and phase identification in type 304 stainless steel-zirconium alloys

# publications[].label
Formation mechanism of delta phase in the as-cast U-10wt%Zr alloy

# publications[].label
Uranium powder production using a hydride-dehydride process

# publications[].label
A zirconium cermet for transuranic isotope storage and burning

# publications[].label
Thermal properties of uranium molybdenum alloys at various stages of phase decomposition

# publications[].label
High temperature interaction behavior at liquid metal-ceramic interfaces

# publications[].label
Ar-ion-milling-induced structural changes of Cu₅₀Zr₄₅Ti₅ metallic glass

# publications[].label
Shielding requirements for mission to mars nuclear engines

# publications[].label
Fluidized Bed Chemical Vapor Deposition of Zirconium Nitride Films

# publications[].label
DEFINING A METAL-BASED WASTE FORM FOR IFR PYROPROCESSING WASTES

# publications[].label
Preparation of uranium-zirconium alloy nuclear fuel elements by PM

# publications[].label
Autonomous multi-purpose floating power system with a compact static pebble bed reactor

# publications[].label
Preparation of U-10Zr Alloys for Irradiation Testing in the Advanced Test Reactor to Enable MARMOT Assessment and Validation

# publications[].label
A Data-driven approach to predicting neutron penetration through media

# publications[].label
Development of an accident-tolerant fuel composite from uranium mononitride (UN) and uranium sesquisilicide (U₃ Si₂) with increased uranium loading

# publications[].label
Actinide distribution in a stainless steel-15 wt% zirconium high-level nuclear waste form

# publications[].label
Fabrication of cermet nuclear fuels designed for the transmutation of transuranic isotopes

# publications[].label
Ion-Exchange Kinetics of Alpha-Zirconium Phosphate Nanoplatelets for Application in Targeted Alpha Therapy

# publications[].label
Monitoring and predicting stress corrosion cracking of long term spent nuclear fuel storage

# publications[].label
Neutronic evaluation of high thermal conductivity UO2-BeO fuel

# publications[].label
Rabbit Delivery System Design and Thermal Analysis for a Versatile Test Reactor Environment

# publications[].label
Challenges in joining advanced ceramic materials: Interface formation of ceramic/metal high-temperature brazes

# publications[].label
Ceramic-ceramic composites and process therefor, nuclear fuels formed thereby, and nuclear reactor systems and processes operated therewith

# publications[].label
Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel

# publications[].tags
12 Responsible Consumption and Production

# publications[].label
Tension metastable fluid detection systems for special nuclear material detection and monitoring

# publications[].label
Alloy waste forms for metal fission products and actinides isolated by spent nuclear fuel treatment

# publications[].label
Analysis of the VTR In-Core Environment with the Rabbit Delivery System Enabling Encapsulated Irradiations

# publications[].label
Transformation enthalpies of uranium-zirconium alloy system

# publications[].label
Measurement of thermal diffusivity of depleted uranium metal microspheres

# publications[].label
Thoria-Based Cermet Nuclear Fuel: Cermet Fabrication and Behavior Estimates

# publications[].label
A sensitivity analysis to predict the neutronics behavior of samples irradiated in the VTR rabbit system

# publications[].label
Chemical partitioning technologies for an ATW system

# publications[].label
An investigation of U-Zr alloy phase diagram using in-situ heating electron diffractometry

# publications[].label
Formation of the Fe23Zr6 phase in an Fe-Zr alloy

# publications[].label
Design of an integrated system to recycle Zircaloy cladding using a hydridemillingdehydride process

# publications[].label
Precursors for the immobilization of radioactive cesium and strontium from spent nuclear fuel

# publications[].label
High temperature super-critical CO<inf>2</inf>-cooled integrated multi-modular thermal reactor

# researcherOn[].label
Radioactive Powder Characterization Equipment for Enhanced Research and Teaching Capability

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
NuSTEM: Nuclear Science, Technology and Education for Molten Salt Reactors

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10ZR  NEUP 18-14741

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# streetAddress
Texas A&M University; Nuclear Engineering; 3133 TAMU

# organizations[]
Texas A&M Engineering Experiment Station (TEES)

# schools[]
Texas A&M Engineering Experiment Station (TEES)

# inTheNews[].label
ANEEL: Thorium-Based Reactor Fuel Could Support A New Wave

# inTheNews[].label
Texas A&M Researchers Developing Clean Nuclear Fuel

# inTheNews[].label
Texas A&M Engineering Plays Key Role In Research Reactor Development

# etdChairOf[].label
Ortega, Luis H. (2009-12). Sintered Bentonite Ceramics for the Immobilization of Cesium- and Strontium-Bearing Radioactive Waste. Doctoral Dissertation.

# etdChairOf[].label
Helmreich, Grant (2010-12). Characterization of Alpha-Phase Sintering of Uranium and Uranium-Zirconium Alloys for Advanced Nuclear Fuel Applications. Master's Thesis.

# etdChairOf[].label
Garcia, Chad (2014-04). Sintering and Thermal Behavior of Uranium Dioxide in Beryllium Oxide Matrix. Master's Thesis.

# etdChairOf[].label
Creasy, John Thomas (2012-02). Thermal Properties of Uranium-Molybdenum Alloys: Phase Decomposition Effects of Heat Treatments. Master's Thesis.

# etdChairOf[].label
Sames, William (2015-05). Additive Manufacturing of Inconel 718 using Electron Beam Melting:  Processing, Post-Processing, & Mechanical Properties. Doctoral Dissertation.

# etdChairOf[].label
Parkison, Adam Joseph (2008-05). Hydride production in zircaloy-4 as a function of time and temperature. Master's Thesis.

# etdChairOf[].label
Arrieta, Marie (2012-08). Low Temperature Chemical Vapor Deposition of Zirconium Nitride in a Fluidized Bed. Master's Thesis.

# etdChairOf[].label
Evans, Jordan Andrew (2017-12). Anisotropic Response of Laser Additively Manufactured Nuclear Alloys to Radiation Damage. Doctoral Dissertation.

# etdChairOf[].label
Woolum, Connor (2014-12). Fabrication and Characterization of Uranium-Molybdenum-Zirconium Alloys. Master's Thesis.

# etdChairOf[].label
Wegener, Jeffrey J. (2008-12). Production of cerium oxide microsheres by an internal gelation sol-gel process. Master's Thesis.

# etdChairOf[].label
Parkison, Adam J (2013-06). Separation of Zirconium from Uranium in U-Zr Alloys Using a Chlorination Process. Doctoral Dissertation.

# etdChairOf[].label
Hausaman, Jeffrey Stephen (2011-12). Hot Extrusion of Alpha Phase Uranium-Zirconium Alloys for TRU Burning Fast Reactors. Master's Thesis.

# etdChairOf[].label
Mews, Paul Aaron (2007-12). Evaluation of zirconium-iron-rhenium alloys as surrogates for a technetium alloy waste form. Master's Thesis.

# etdChairOf[].label
Humrickhouse, Carissa Joy (2012-05). Characterization of Thermal Properties of Depleted Uranium Metal Microspheres. Master's Thesis.

# etdChairOf[].label
Eichel, Daniel (2013-08). Atomic Diffusion in the Uranium-50wt% Zirconium Nuclear Fuel System. Master's Thesis.

# etdChairOf[].label
Sudderth, Laura (2015-04). Zirconium Nitride Coating Fabrication via Fluidized Bed Chemical Vapor Deposition. Master's Thesis.

# etdChairOf[].label
Irukuvarghula, Sandeep (2013-08). Solid State Phase Transformations in Uranium-Zirconium Alloys. Doctoral Dissertation.

# etdChairOf[].label
Garnetti, David J. (2009-12). Uranium Powder Production Via Hydride Formation and Alpha Phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications. Master's Thesis.

# etdChairOf[].label
Hogelin, Thomas Russell (2010-12). Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing. Master's Thesis.

# etdChairOf[].label
Mews, Kathryn Ann Wright (2013-05). Methods for Investigating Gas Bubble Formation in Uranium-Zirconium Alloys. Master's Thesis.

# etdChairOf[].label
Barnhart, Brian A. (2013-08). Characterization of Zr-Fe-Cu Alloys for an Inert Matrix Fuel for Nuclear Energy Applications. Master's Thesis.

# etdChairOf[].label
Ahn, Sangjoon (2013-07). Comprehensive Investigation of the Uranium-Zirconium Alloy System: Thermophysical Properties, Phase Characterization and Ion Implantation Effects. Doctoral Dissertation.

# etdChairOf[].label
Martinez, John Calvin (2015-05). Hydrogen Interactions in Zirconium Alloys for Nuclear Applications. Master's Thesis.

# etdChairOf[].label
Kelley, Randy Dean (2010-08). Design of an Integrated System to Recycle Zircaloy Cladding Using a Hydride-Milling-Dehydride Process. Doctoral Dissertation.

# etdChairOf[].label
Totemeier, Aaron Robert (2015-12). Helium Ion Implantation in Zirconium: Bubble Formation & Growth. Doctoral Dissertation.

# etdChairOf[].label
Goddard, Braden (2009-12). Development of a Real-Time Detection Strategy for Material Accountancy and Process Monitoring During Nuclear Fuel Reprocessing Using the Urex+3A Method. Master's Thesis.

# etdChairOf[].label
Thompson, Chad 1984- (2012-12). A Rotating Electrode System for the Generation of Metal Alloy Microspheres. Master's Thesis.

# etdChairOf[].label
Kuhr, Samuel Houston (2012-08). An Electrolytic Method to Form Zirconium Hydride Phases in Zirconium Alloys with Morphologies Similar to Hydrides Formed in Used Nuclear Fuel. Master's Thesis.

# etdChairOf[].label
Clemens, Jeffrey Tyler (2014-05). Radiochemical Transformation of High Pressure Methane under Gamma, Electron, and Neutron Irradiation. Master's Thesis.