Nuclear Engineering ETDs
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Theses/Dissertations from 2025
Development and Demonstration of Scalable Fluoride Salt Pump Bearings for FHRs, Yuqi Liu
Theses/Dissertations from 2024
Study of Valves and Performance Parameters Quantification for SMART Valves Control System, Anutam Bairagi
Deterministic Transport of Coupled Energetic Light-Ions and Neutrons with Application to Inertial Confinement Fusion, Kyle Beling
Improving Criticality Safety Benchmark Coverage by Developing a Benchmark Evaluation of the UNM AGN-201M Reactor, Rowdy Davis
Design and Analysis of Free Piston Stirling Engines for Microreactor Applications, Phat D. Doan
Methods for Efficient Computation of Neutron Multiplicity Distributions and SNM Sample Characterization, Jawad Ribhi Moussa
Coupled Monte Carlo and Adjoint Depletion Sensitivity Coefficient Methods, Benjamin R. Murphy
TRAINING MACHINE LEARNING ALGORITHMS FOR THE TRANSIENT STARTUP OF A LONG-LIFE MODULAR MICROREACTOR, Ahmad N. Shaheen
DEVELOPMENT AND EVALUATION OF MUON SCATTERING TOMOGRAPHY RECONSTRUCTION TECHNIQUES FOR SPENT FUEL VERIFICATION, Jesus J. Valencia
Theses/Dissertations from 2023
MINIATURE, SUBMERSIBLE ELECTROMAGNETIC PUMPS OF MOLTEN LEAD AND SODIUM FOR GEN-IV NUCLEAR REACTORS DEVELOPMENT, Ragai M. Altamimi
Application of an Empirical Density Law via Python for Aqueous Plutonium Chloride Systems for MCNP6, Riley Bulso
Measurements of scintillation light quenching for protons in rare-earth inorganic scintillators, Tatiana Nathaly Espinoza
Physical Properties of Copper Niobium Nanolamellar Composites Fabricated by Accumulative Roll Bonding, Jared Justice
Material Reliability for a Molten Chloride Salt System, Aaron A.H. Overacker
Understanding the Behavior of Upper Subcritical Limit Calculations, Bobbi Riedel
Application of an Empirical Density Law via Python for Aqueous Plutonium Nitrate Systems, Tara L. Robertson
A Comparison of Fixed Versus Moving Eulerian Meshes for 1-D Radiative Shock Problems, Dylan Weatherred
Sensitivity and Uncertainty Analysis of Inertial Confinement Fusion Experiments, Colin A. Weaver
Theses/Dissertations from 2022
Joining of Candidate Materials for Lead-Cooled Fast Reactors, Brandon M. Bohanon
Experimental Investigations on Boiling Heat Transfer Characteristics of Accident-Tolerant-Fuel and Traditional Claddings, Mingfu He Mr.
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design, Alexis Maldonado
Simulation of Thermal Radiation Transport in Stochastic Media with Nonlinear Temperature Dependence, Corey Michael Skinner
Computational Methods, Investigations, and Codes to Support Corrosion Experiments in Molten Lead and Transfer to Reactor Conditions, Khaled A. Talaat
THE EFFECTS OF A POWER ITERATION-BASED K-EIGENVALUE SOLVER FOR VARIOUS SUBCRITICAL PARAMETERS AND CALCULATIONS, Daniel H. Timmons
Theses/Dissertations from 2021
MONTE CARLO PERTURBATION ANALYSIS OF DIMENSION AND DENSITY VARIATIONS OF THE ANNULAR CORE RESEARCH REACTOR MODEL FUEL, Karissa Currie
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
CHARACTERIZATION OF PARTIAL CHARGE COLLECTION INDUCED BY NEUTRON DAMAGE IN HIGH-PURITY GERMANIUM DETECTORS, James W. Evans
Characterization of Uranium Foil Irradiations at the WSU TRIGA Reactor Using a New Reactor Model in SCALE, Kimberly A. Hinrichs
Modeling and Simulation of Stochastic Neutron and Cumulative Deposited Fission Energy Distributions, Patrick O'Rourke
A Two-Dimensional Spherical-Polar Multigroup Discrete Ordinates Code for Atmospheric Particle Transport, Daniel T. Wakeford
Theses/Dissertations from 2019
APPLICATION OF MACHINE LEARNING TO CHF MODELLING, Mingfu He Mr
Developing a simulation tool for evaluating in-motion detector systems (LA-UR-18-29139), Brian Jennings
Experimental Investigation of Steady-state and Transient Flow Boiling Critical Heat Flux, Soon Kyu Lee
NEUTRONIC AND CFD-THERMAL HYDRAULIC ANALYSES OF VERY-SMALL, LONG-LIFE, MODULAR (VSLLIM) REACTOR, Luis M. Palomino
INTERROGATION OF SPENT NUCLEAR FUEL CASKS USING COSMIC-RAY MUON COMPUTED TOMOGRAPHY, Daniel C. Poulson
An Experimental and Numerical Investigation of Flow Accelerated FLiBe Corrosion, David B. Weitzel
Theses/Dissertations from 2018
Design and Characterization of Systems for Direct Spatial Imaging of Low-Energy Gamma-Radiation Sources, Phoenix Baldez
Development of The University of New Mexico Spectrometer for High-Resolution Fission Product Yield Data, Richard Emery Blakeley
Development of a Positron-Emitting Surrogate Microsphere for Image-Based Dosimetry in Yttrium-90 Radioembolization Therapy, Gregory D. Chambers
Radiation Effects in Metal Oxides and Carbides, Benjamin Jackson Cowen
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
Development of a Novel Framework for the Application of Signature Based Safeguards (SBS) to Pyroprocessing, Philip Leo Lafreniere
Investigating the Electrodeposition of Plutonium and Curium for Safeguarding the Electrorefiner, Chantell L. Murphy
INVESTIGATION OF THE FORMATION OF γꞌꞌ PRECIPITATES UNDER ION IRRADIATION AND ELEVATED TEMPERATURE ENVIRONMENTS, James R. Pike
Sonomechanical Enhanced Sparging Techniques for Advanced Reactor Applications, Floren V. Rubio
Patient Specific Radiation Doses From Projection Radiography Images: Improving the Accuracy of Low Dose Radiation Calculations, Daniel J. Sandoval
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
The Inverse Kinetics Method and Its Application to the Annular Core Research Reactor, Thomas A. Ball
TIME-OF-FLIGHT AND ENERGY LOSS ANALYSIS ON THE UNM FISSION FRAGMENT SPECTROMETER, Shelby Fellows
Asymptotic Neutronic Solutions for Fast Burst Reactor Design, Edward L. Hobbs
Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-cooled High-temperature Reactors, Joel T. Hughes
High Precision Refractive Index Measurement Techniques Applied to the Analysis of Neutron Damage and Effects in CaF2 Crystals, Joseph P. Morris Ph.D.
Examination of color center formation in CaF2 crystals when exposed to gamma and mixed neutron/gamma fields, Sara M. Pelka
Evaluation of Energy Released from Nuclear Criticality Excursions in Process Solutions, Corey Michael Skinner
Remote Handled Disposal Enhancement at the Waste Isolation Pilot Plant, Philip Theisen
Theses/Dissertations from 2016
An Ionization Chamber for High Resolution Fission Product Spectroscopy, James Cole
Doppler Temperature Coefficient Calculations Using Adjoint-Weighted Tallies and Continuous-Energy Cross Sections in MCNP6, Matthew A. Gonzales
PREDICTING ACTIVATION OF EXPERIMENTS INSIDE THE ANNULAR CORE RESEARCH REACTOR, Joseph Greenberg
Reduced-Order Monte Carlo Modeling of Radiation Transport in Random Media, Aaron J. Olson
Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations, Mario Ivan Ortega
Fokker-Planck-Based Acceleration for SN Equations with Highly Forward Peaked Scattering in Slab Geometry, Japan K. Patel
Advanced Stochastic Collocation Methods for Polynomial Chaos in RAVEN, Paul W. Talbot
Thin film AlSb carrier transport properties and room temperature radiation response, Erin Vaughan
Theses/Dissertations from 2015
Space-Time Kinetics of the AGN-201M Research Reactor at the University of New Mexico, Douglas Bowen
A Computationally Efficient Moment-Preserving Monte Carlo Electron Transport Method with Implementation in Geant4, David Dixon
Characterization of the Neutron Irradiation System for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories, Jr. Manuel Franco
Ionization Chamber Design, Development, and Testing for the UNM Fission Fragment Spectrometer, Lena Heffern
EXPERIMENTAL STUDIES OF THE CHEMICAL EFFECTS OF ZINC-BEARING MATERIALS FOLLOWING A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER REACTOR, David Allan Pease
MULTI-PHYSICS DESIGN AND ANALYSES OF LONG LIFE REACTORS FOR LUNAR OUTPOSTS, Timothy M. Schriener
PREDICTING THE SENSITIVITY OF A BERYLLIUM/SCINTILLATOR FUSION NEUTRON DETECTOR COMBINING EXPERIMENTAL METHODS AND MONTE CARLO MODELS, Jedediah Styron
ENVIRONMENTAL RADIATION DOSE ASSESSMENT AND VALIDATION FOR URANIUM HEXAFLUORIDE STORAGE MANAGEMENT, Shiaw-Der Su
SERPENT Modeling of the Transient Reactor Test Facility and Comparison with Measured Experimental Data, Joseph Templeton
Theses/Dissertations from 2014
Radiation Damage in Permanent Magnet Lenses, Christopher Danly
An Sn Application of Homotopy Continuation in Neutral Particle Transport, Nicholas Myers
Efficient Multiphysics Coupling for Fast Burst Reactors in Slab Geometry, Japan Patel
Moment-Based Accelerators for Kinetic Problems with Application to Inertial Confinement Fusion, William Taitano
Examining Thin Film AlSb for Room Temperature Gamma Detectors, Erin Vaughan
INNOVATIVE OPEN AIR BRAYTON COMBINED CYCLE SYSTEMS FOR THE NEXT GENERATION NUCLEAR POWER PLANTS, Bahman Zohuri
Theses/Dissertations from 2013
A time-of-flight spectrometer for fission fragment identification, Richard Blakeley
Modeling and Analysis of Actinide Diffusion Behavior in Irradiated Metal Fuel, Paul Edelmann
A moment-preserving single-event Monte Carlo model of electron and positron energy-loss straggling, Matthew Gonzales
Eigenfunction expansion of the time and space-dependent neutron survival probability equation, Ryan J. Kamm
Dual Neutral Particle Beam Interrogation of Intermodal Shipping Containers for Special Nuclear Material, Rodney Keith
Comparing water to DNA for simulation of Auger electron direct damage to DNA using Geant4, Elliott Leonard
An ionization chamber for fission fragment analysis, Drew Mader
Behavior and measurement of distributed sources in a shielding matrix using gamma spectroscopy, Jacob Miller
ADVANCED APPLICATIONS OF COSMIC-RAY MUON RADIOGRAPHY, John Perry
Quantification and propagation of nuclear data uncertainties, Michael Rising
An Effective Methodology for Thermal-Hydraulics Analysis of a VHTR Core and Fuel Elements, Boyce Travis
