Theses from 2024
Investigating Accident-Tolerant Cladding in a Molten Salt-Cooled Micro-Reactor using Multi-Physics Analysis and Uncertainty Quantification, Alexander Niles Foutch
Validation of Athlet with Purdue University Multi-Dimensional Integral Test Assembly (PUMA) Test, Emin Fatih Ozdem
Simulation of lC Circuits in Cylindrical Photoemission Driven Cavities using Coupled Monte Carlo and Particle-in-Cell Codes, Ravi Sanjay Shastri
Computational Fluid Dynamics Analysis of Thermal-Hydraulic Phenomena in Nuclear Reactor Systems, Mehedi Hasan Tusar
Theses from 2022
Modeling the reactor time-dependent delayed particle tail with Monte Carlo N-Particle (MCNP) version 6.2, Eli James Boland
Particle swarm optimization for critical experiment design, Cole Michael Kostelac
Characterization of cermet fuel for nuclear thermal propulsion (NTP), James Floyd Mudd
Feasibility of a critical experiment utilizing uranium dioxide-beryllium oxide with neutron spectrum shifting capabilities, Ashley Rachel Raster
Validation of ATHLET-CD with CORA-28 test, Murat Tuter
Theses from 2021
Development of complex lattice cell in benchmark model of particle bed critical system, Elijah Chamberlain Lutz
Theses from 2020
Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation, Nishant Raghav Pillai
Theses from 2018
Development and Monte Carlo validation of a finite element reactor analysis framework, Wayne J. Brewster
An investigation into the effects of ion tracks on α-quartz, Bryant Alan Kanies
Fuel burnup simulation and analysis of the Missouri S&T Reactor, Joshua Hinkle Rhodes
Modulated photothermal radiometry: Detector sensitivity study and experimental setup, Jessica Nicole Seals
Customized multi-group cross section generation with NJOY for discrete ordinates computed tomography and radiography simulation, Steven Michael Wagstaff
Theses from 2017
The viability of ADVANTG deterministic method for synthetic radiography generation, Andrew Albert Bingham
Design and analysis of a passive heat removal system for a small modular reactor using STAR CCM+, Raymond Michael Fanning
A study of the potential applications of AM241, and determining the feasibility of using Gamma spectroscopy for future physical validation, Eric A. Feissle
Comparison of ²⁵²Cf time correlated induced fission with AmLi induced fission on fresh MTR research reactor fuel, Jay Prakash Joshi
CFD validation and scaling of condensation heat transfer, Varun Kalra
Analysis and implementation of accident tolerant nuclear fuels, Benjamin Joseph Prewitt
Theses from 2016
Attenuation properties of cement composites: Experimental measurements and Monte Carlo calculations, Raul Florez
Synthesis of Radioactive Nanostructures in a Research Nuclear Reactor, Maria Camila Garcia Toro
Deterministic simulation of thermal neutron radiography and tomography, Rajarshi Pal Chowdhury
Thermal characterization of phase change materials for thermal energy storage, Rami Mohammad Reda Saeed
A feasibility study of a nuclear power plant with no moving parts, Jonathan Mark Schattke
Theses from 2015
Impact of configuration variations on small modular reactor core performance, William Kirby Compton
Neutronic analysis of light water Small Modular Reactor with flexible fuel configurations, Brendan Dsouza
Computer aided detection of oral lesions on CT images, Shaikat Mahmood Galib
Initial fuel possibilities for the Thorium Molten Salt Reactor, Dustin Gage Green
Computer aided diagnosis of oral cancer: Using time-step CT images, Jonathan T. Scott
Theses from 2014
Experimental investigation of the pebble bed structure by using gamma ray tomography, Fadha Shakir Ahmed
Feasibility study of a two-fluid small modular molten salt reactor with in core heat removal capability, Brandon James Lahmann
Determination of minor and trace elements concentration in kidney stones using elemental analysis techniques, Anjali Srivastava
Theses from 2013
Insufficient CT data reconstruction based on directional total variation (DTV) regularized maximum likelihood expectation maximization (MLEM) method, Fahima Fahmida Islam
A new approach to nuclear safeguard enhancement through radionuclide profiling, Aaron Dawon Peterson
CFD simulation of void flow in ECCS, Lifeng Wang
Theses from 2012
Wavelet based contrast limited histogram equalization for contrast enhancement of digital mammography, Ashish Vighnahar Avachat
Hot channel determination and burnup analysis of Missouri University of Science and Technology Research Nuclear Reactor, Kelly Christopher Rogers O'Bryant
Determination of linear attenuation coefficients of chemically bonded phosphate ceramics, Jason Joseph Pleitt
Verification of a Monte Carlo model of the Missouri S&T reactor, Brad Paul Richardson
Theses from 2011
Contrast enhancement of digital mammography based on multi-scale analysis, Muhammad Imran Khan Abir
Simulation of the field electron emission characteristics of a flat panel X-ray source, Chrystian Mauricio Posada Arbeláez
Production and characterization of supported palladium nanoparticles on multiwalled carbon nanotubes by gamma irradiation, Jessika Viviana Rojas Marin
Density determination of tristructural-isotropic nuclear fuel using multiple projection x-ray radiography, Frank Angelo Strantz
Upgrade and simulation of the subcritical assembly at Missouri University of Science and Technology, Lucas Powelson Tucker
Theses from 2010
Characterization of the neutron flux spectrum at the Missouri University of Science and Technology Research Reactor, Zachary Andrew Kulage
Theses from 2009
Mass optimization studies of reactivity control schemes and radiation shielding options for space nuclear reactors, Aaron E. Craft
Analogy based modeling of natural convection, Vaibhav Khane
Theses from 2008
Feasibility study of plutonium based MOX fuel online burnup analysis using gamma spectroscopy, Matthew L. Dennis
Modeling the effect of plastic flow localization on deformation and fracture of stainless steel, Michael Louis Lampe
Theses from 2007
Equivalent circuit for transient conduction and convection systems, Bassam Sabry Mohammad Abdelnabi
One-group interfacial area transport equation for horizontal two-phase flow with 90-degree bend, Kennard Callender
Bonding Technetium-99m to hydroxyapatite particles: Opportunity to use hydroxyapatite as a means to remove Tc-99 from nuclear waste streams, Michelle Elaine Minard
Theses from 2004
Using PARET and CONVEC to perform accident analysis of the University of Missouri-Rolla Nuclear Reactor, Christopher M. Carroll
Homogenization effects on neutron flux Monte Carlo calculations for an accelerator driven system, Jamie Marlene Ferrero
Natural convection heat transfer of hydrophilic particle suspension in a rectangular cell, Izumi Hagiwara
An evaluation of domestic nuclear reactor facility security in the post September 11 environment: perspectives from the national, state, and site-specific levels, Tracia Lynn West
Theses from 2003
Determination of void swelling in a PWR baffle bolt due to fast neutron exposure, Tyson Derrik Bourbina
Investigation of the wake flow structure resulting from a bubble's tail and a change in flow channel geometry, Michel Amasa Call
Flow structure in the near-wake of single solid and fluid objects as measured by particle image velocimetry, Hidekazu No
Theses from 2001
Atmospheric dispersion and dose estimates for research reactors, Matthew Clark Adler
DUPoly radiation shielding effectiveness, Scott Patrick Rutenkroger
Theses from 2000
Implementation of the finite element method in a nodal transport program to allow for heterogeneous geometries, Micheal Addison Smith
Theses from 1999
Dynamic finite element modeling of Charpy impact test with various geometry in 2-D and 3-D analysis using ABAQUS, Chong Wan Kwon
Multimedia web-based learning environment for topics in radiation decay, Rodney Allen Rossow
Design and analysis of an accelerator based medical isotope production facility, Jeffrey Dean Shelton
Thermal power calibration of the University of Missouri-Rolla research reactor, Eric Paul Stevenson
Theses from 1997
Determination of moderator temperature coefficient in a pressurized water reactor using neutron and temperature noise analysis, Clinton Eugene Gross
Application of artificial neural network technology to loose parts monitoring systems, Rodney Galen Pickard
Calculated neutron dose rates from a plutonium source using the Monte Carlo method, Erik F. Shores
Theses from 1996
Gamma-ray dose rate from a spent PWR fuel assembly using the Monte Carlo technique, Ahmet Bozkurt
Neutron radiography of granite and marble, Mevlut Guvendik
Dynamic finite element analysis of Charpy impact tests for use in nuclear power plant life extension, Scott E. Sidener
Theses from 1995
Direct solutions to the even-parity neutron transport equation, Scott Walter Drumm
Nuclear fuel pellet inspection using machine vision and artificial neural networks, Mark Le Roy Kelly
Effects of specimen size reduction on the transition curve of the Charpy V-notch impact test, Lonnie Eugene Schubert
Theses from 1994
Dose rate measurements of the highly-enriched uranium fuel at the University of Missouri-Rolla reactor, Michelle Lynn Hill
Neutron fluence at the pressure vessel of a pressurized water reactor determined with the MCNP code, Peter Gyula Laky
Theses from 1993
A thermocouple based proton beam profile monitor, Phillip D. Ferguson
Nature of incorporated water in hydrated potassium silicate glasses, William Joseph Reich
Theses from 1992
C-THERMOS : an integral neutron transport code with a cold neutron scattering kernel option, Yonkai Liao
Comparison of measured and calculated transmutation in copper at spallation neutron sources, Timothy Brian O'Hearn
Theses from 1991
Dose rate determination of the highly-enriched uranium fuel at the University of Missouri-Rolla Reactor in preparation for transportation, Alice Ann Netzer
Analytical computer package for the University of Missouri-Rolla reactor, Tracy John Orf
Theses from 1990
Application of adaptive zoning to the finite element solution of the one-group diffusion equation in two dimensions, Bryan Edward Audsley
Theses from 1989
Neutronics study of the conversion of the University of Missouri-Rolla reactor to low enriched uranium fuel, Lorne J. Covington
Flow analysis of a pressurized water reactor core, Charles Ramon Daily
Determination of characteristics of the University of Missouri-Rolla reactor highly-enriched uranium fuel using the ORIGEN2 computer code, Jeffery Joel Smith
Theses from 1988
Space based neutral particle beam platform prime power system and mass analysis, Bryan John Daiber
Effect of an annular connection between the plasma source and flux conserver on the properties of CTX spheromaks, Charles Matthew Hart
The influence of specimen size on Charpy impact testing of unirradiated HT-9, Brian Scott Louden
Theses from 1987
Mechanical and neutronic properties of neutron absorbing materials, Donald James Buth
X-ray imaging system for the Missouri Magnetic Mirror Prototype Experiment, Curtis David Eshelman
Obtaining the prime implicants of a system by utilizing dynamic core allocation, Linda M. Farrell
Data analysis for the soft x-ray imaging system, Houken Tseng
Theses from 1986
Fuel loading for a low-leakage core in a pressurized water reactor, Omar Ivan Aguilar
Dimensional change correlations for 20% cold worked AISI 316 stainless steel for fusion applications, Robert Wayne Clark
