Nuclear Engineering ETDs

Nuclear Engineering ETDs

 

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Theses/Dissertations from 2025

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Development and Demonstration of Scalable Fluoride Salt Pump Bearings for FHRs, Yuqi Liu

Theses/Dissertations from 2024

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Study of Valves and Performance Parameters Quantification for SMART Valves Control System, Anutam Bairagi

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Deterministic Transport of Coupled Energetic Light-Ions and Neutrons with Application to Inertial Confinement Fusion, Kyle Beling

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Improving Criticality Safety Benchmark Coverage by Developing a Benchmark Evaluation of the UNM AGN-201M Reactor, Rowdy Davis

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Design and Analysis of Free Piston Stirling Engines for Microreactor Applications, Phat D. Doan

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Methods for Efficient Computation of Neutron Multiplicity Distributions and SNM Sample Characterization, Jawad Ribhi Moussa

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Coupled Monte Carlo and Adjoint Depletion Sensitivity Coefficient Methods, Benjamin R. Murphy

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TRAINING MACHINE LEARNING ALGORITHMS FOR THE TRANSIENT STARTUP OF A LONG-LIFE MODULAR MICROREACTOR, Ahmad N. Shaheen

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DEVELOPMENT AND EVALUATION OF MUON SCATTERING TOMOGRAPHY RECONSTRUCTION TECHNIQUES FOR SPENT FUEL VERIFICATION, Jesus J. Valencia

Theses/Dissertations from 2023

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MINIATURE, SUBMERSIBLE ELECTROMAGNETIC PUMPS OF MOLTEN LEAD AND SODIUM FOR GEN-IV NUCLEAR REACTORS DEVELOPMENT, Ragai M. Altamimi

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Application of an Empirical Density Law via Python for Aqueous Plutonium Chloride Systems for MCNP6, Riley Bulso

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Measurements of scintillation light quenching for protons in rare-earth inorganic scintillators, Tatiana Nathaly Espinoza

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Physical Properties of Copper Niobium Nanolamellar Composites Fabricated by Accumulative Roll Bonding, Jared Justice

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Material Reliability for a Molten Chloride Salt System, Aaron A.H. Overacker

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Understanding the Behavior of Upper Subcritical Limit Calculations, Bobbi Riedel

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Application of an Empirical Density Law via Python for Aqueous Plutonium Nitrate Systems, Tara L. Robertson

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A Comparison of Fixed Versus Moving Eulerian Meshes for 1-D Radiative Shock Problems, Dylan Weatherred

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Sensitivity and Uncertainty Analysis of Inertial Confinement Fusion Experiments, Colin A. Weaver

Theses/Dissertations from 2022

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Joining of Candidate Materials for Lead-Cooled Fast Reactors, Brandon M. Bohanon

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Experimental Investigations on Boiling Heat Transfer Characteristics of Accident-Tolerant-Fuel and Traditional Claddings, Mingfu He Mr.

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Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design, Alexis Maldonado

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Simulation of Thermal Radiation Transport in Stochastic Media with Nonlinear Temperature Dependence, Corey Michael Skinner

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Computational Methods, Investigations, and Codes to Support Corrosion Experiments in Molten Lead and Transfer to Reactor Conditions, Khaled A. Talaat

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THE EFFECTS OF A POWER ITERATION-BASED K-EIGENVALUE SOLVER FOR VARIOUS SUBCRITICAL PARAMETERS AND CALCULATIONS, Daniel H. Timmons

Theses/Dissertations from 2021

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MONTE CARLO PERTURBATION ANALYSIS OF DIMENSION AND DENSITY VARIATIONS OF THE ANNULAR CORE RESEARCH REACTOR MODEL FUEL, Karissa Currie

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MONTE CARLO PERTURBATION ANALYSIS OF FUEL TEMPERATURE VARIATIONS IN THE MCNP MODEL OF THE ANNULAR CORE RESEARCH REACTOR, Melissa Andrea Moreno

Theses/Dissertations from 2020

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CHARACTERIZATION OF PARTIAL CHARGE COLLECTION INDUCED BY NEUTRON DAMAGE IN HIGH-PURITY GERMANIUM DETECTORS, James W. Evans

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Characterization of Uranium Foil Irradiations at the WSU TRIGA Reactor Using a New Reactor Model in SCALE, Kimberly A. Hinrichs

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Modeling and Simulation of Stochastic Neutron and Cumulative Deposited Fission Energy Distributions, Patrick O'Rourke

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A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport, Daniel T. Wakeford

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A Forward Analytic Model of Neutron Time-of-Flight Signals with Single Elastic Scattering and Beamline Attenuation for Inferring Ion Temperatures from MagLIF Experiments, Colin A. Weaver

Theses/Dissertations from 2019

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DEVELOPMENT OF WIRELESS PEBBLE FOR PACKED BED HEAT TRANSFER MEASUREMENTS AND MACHINE LEARNING-AIDED ACCIDENT DIAGNOSIS FOR LOSS OF FLOW ACCIDENT (LOFA), Dongjune Chang

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APPLICATION OF MACHINE LEARNING TO CHF MODELLING, Mingfu He Mr

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Developing a simulation tool for evaluating in-motion detector systems (LA-UR-18-29139), Brian Jennings

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Experimental Investigation of Steady-state and Transient Flow Boiling Critical Heat Flux, Soon Kyu Lee

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NEUTRONIC AND CFD-THERMAL HYDRAULIC ANALYSES OF VERY-SMALL, LONG-LIFE, MODULAR (VSLLIM) REACTOR, Luis M. Palomino

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INTERROGATION OF SPENT NUCLEAR FUEL CASKS USING COSMIC-RAY MUON COMPUTED TOMOGRAPHY, Daniel C. Poulson

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An Experimental and Numerical Investigation of Flow Accelerated FLiBe Corrosion, David B. Weitzel

Theses/Dissertations from 2018

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Design and Characterization of Systems for Direct Spatial Imaging of Low-Energy Gamma-Radiation Sources, Phoenix Baldez

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Development of The University of New Mexico Spectrometer for High-Resolution Fission Product Yield Data, Richard Emery Blakeley

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Development of a Positron-Emitting Surrogate Microsphere for Image-Based Dosimetry in Yttrium-90 Radioembolization Therapy, Gregory D. Chambers

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Radiation Effects in Metal Oxides and Carbides, Benjamin Jackson Cowen

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An exploration of the optical detection of ionizing radiation utilizing modern optics technology, Sean D. Fournier, Adam Hecht, Cassiano de Oliveira, Jeffrey B. Martin, Richard K. Harrison, and Charles Potter

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Development of a Novel Framework for the Application of Signature Based Safeguards (SBS) to Pyroprocessing, Philip Leo Lafreniere

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Investigating the Electrodeposition of Plutonium and Curium for Safeguarding the Electrorefiner, Chantell L. Murphy

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INVESTIGATION OF THE FORMATION OF γꞌꞌ PRECIPITATES UNDER ION IRRADIATION AND ELEVATED TEMPERATURE ENVIRONMENTS, James R. Pike

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Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications, Floren V. Rubio

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Patient Specific Radiation Doses From Projection Radiography Images: Improving the Accuracy of Low Dose Radiation Calculations, Daniel J. Sandoval

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Analysis of Double-Wall and Twisted-Tube Heat Exchanger Concepts for use in Fluoride Salt-Cooled High-Temperature Reactors, Bryan M. Wallace

Theses/Dissertations from 2017

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The Inverse Kinetics Method and Its Application to the Annular Core Research Reactor, Thomas A. Ball

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TIME-OF-FLIGHT AND ENERGY LOSS ANALYSIS ON THE UNM FISSION FRAGMENT SPECTROMETER, Shelby Fellows

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Asymptotic Neutronic Solutions for Fast Burst Reactor Design, Edward L. Hobbs

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Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-cooled High-temperature Reactors, Joel T. Hughes

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High Precision Refractive Index Measurement Techniques Applied to the Analysis of Neutron Damage and Effects in CaF2 Crystals, Joseph P. Morris Ph.D.

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Examination of color center formation in CaF2 crystals when exposed to gamma and mixed neutron/gamma fields, Sara M. Pelka

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Evaluation of Energy Released from Nuclear Criticality Excursions in Process Solutions, Corey Michael Skinner

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TIME AND ENERGY CHARACTERIZATION OF A NEUTRON TIME OF FLIGHT DETECTOR USING A NOVEL COINCIDENCE METHOD FOR CONSTRAINING NEUTRON YIELD, ION TEMPERATURE AND LINER DENSITY MEASUREMENTS FROM MAGLIF EXPERIMENTS, Jedediah Styron

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Remote Handled Disposal Enhancement at the Waste Isolation Pilot Plant, Philip Theisen

Theses/Dissertations from 2016

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An Ionization Chamber for High Resolution Fission Product Spectroscopy, James Cole

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Doppler Temperature Coefficient Calculations Using Adjoint-Weighted Tallies and Continuous-Energy Cross Sections in MCNP6, Matthew A. Gonzales

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PREDICTING ACTIVATION OF EXPERIMENTS INSIDE THE ANNULAR CORE RESEARCH REACTOR, Joseph Greenberg

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A Novel Neutron Recoil Spectrometer Concept Utilizing Heavy-Ion Recoils and Time- and Spatially-Resolved Sensor, Joel Long

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Use of Chemical and Isotopic Signatures to Distinguish Between Uranium Mill-Related and Naturally Occurring Groundwater Constituents at the Bluewater Disposal Site, Curtis McHaley

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Reduced-Order Monte Carlo Modeling of Radiation Transport in Random Media, Aaron J. Olson

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Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations, Mario Ivan Ortega

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Fokker-Planck-Based Acceleration for SN Equations with Highly Forward Peaked Scattering in Slab Geometry, Japan K. Patel

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Advanced Stochastic Collocation Methods for Polynomial Chaos in RAVEN, Paul W. Talbot

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Thin film AlSb carrier transport properties and room temperature radiation response, Erin Vaughan

Theses/Dissertations from 2015

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Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico, Douglas Bowen

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A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4, David Dixon

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Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR), Amy Drumm

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Characterization of the Neutron Irradiation System for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories, Jr. Manuel Franco

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Ionization Chamber Design, Development, and Testing for the UNM Fission Fragment Spectrometer, Lena Heffern

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IDENTIFICATION OF ELECTROREFINER AND CATHODE PROCESSING FAILURE MODES AND DETERMINATION OF SIGNATURE-SIGNIFICANCE FOR INTEGRATION INTO A SIGNATURE BASED SAFEGUARDS FRAMEWORK FOR PYROPROCESSING, Philip Lafreniere

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EXPERIMENTAL STUDIES OF THE CHEMICAL EFFECTS OF ZINC-BEARING MATERIALS FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR, David Allan Pease

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MULTI-PHYSICS DESIGN AND ANALYSES OF LONG LIFE REACTORS FOR LUNAR OUTPOSTS, Timothy M. Schriener

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PREDICTING THE SENSITIVITY OF A BERYLLIUM/SCINTILLATOR FUSION NEUTRON DETECTOR COMBINING EXPERIMENTAL METHODS AND MONTE CARLO MODELS, Jedediah Styron

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ENVIRONMENTAL RADIATION DOSE ASSESSMENT AND VALIDATION FOR URANIUM HEXAFLUORIDE STORAGE MANAGEMENT, Shiaw-Der Su

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SERPENT Modeling of the Transient Reactor Test Facility and Comparison with Measured Experimental Data, Joseph Templeton

Theses/Dissertations from 2014

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A TECHNIQUE FOR MEASURING THE TIME RESPONSE AND THROUGH-PUT DELAY OF NEUTRON TIME-OF-FLIGHT (nTOF) SCINTILLATION DETECTORS USING COSMIC RADIATION IN A COINCIDENCE SYSTEM, Michael Bonura

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Radiation Damage in Permanent Magnet Lenses, Christopher Danly

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Facility-Specific Radiation Exposure Risks and Their Implications for Radiation Workers at Department of Energy Laboratories, Adam Davis

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An Sn Application of Homotopy Continuation in Neutral Particle Transport, Nicholas Myers

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Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry, Japan Patel

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SIMULATIONS OF SPACE RADIATION INTERACTIONS WITH MATERIALS, WITH APPLICATION TO DOSE ESTIMATES FOR LUNAR SHELTER AND ABOARD THE INTERNATIONAL SPACE STATION, Tai Pham

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Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion, William Taitano

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Examining Thin Film AlSb for Room Temperature Gamma Detectors, Erin Vaughan

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INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS, Bahman Zohuri

Theses/Dissertations from 2013

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A time-of-flight spectrometer for fission fragment identification, Richard Blakeley

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Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel, Paul Edelmann

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A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling, Matthew Gonzales

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Eigenfunction expansion of the time and space-dependent neutron survival probability equation, Ryan J. Kamm

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Dual Neutral Particle Beam Interrogation of Intermodal Shipping Containers for Special Nuclear Material, Rodney Keith

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Comparing water to DNA for simulation of Auger electron direct damage to DNA using Geant4, Elliott Leonard

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An ionization chamber for fission fragment analysis, Drew Mader

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Behavior and measurement of distributed sources in a shielding matrix using gamma spectroscopy, Jacob Miller

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ADVANCED APPLICATIONS OF COSMIC-RAY MUON RADIOGRAPHY, John Perry

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Quantification and propagation of nuclear data uncertainties, Michael Rising

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MOBILE, HYBRID COMPTON/CODED APERTURE IMAGING FOR DETECTION, IDENTIFICATION AND LOCALIZATION OF GAMMA-RAY SOURCES AT STAND-OFF DISTANCES, Shawn Tornga

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An Effective Methodology for Thermal-Hydraulics Analysis of a VHTR Core and Fuel Elements, Boyce Travis