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Theses from 2024

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Investigating Accident-Tolerant Cladding in a Molten Salt-Cooled Micro-Reactor using Multi-Physics Analysis and Uncertainty Quantification, Alexander Niles Foutch

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Validation of Athlet with Purdue University Multi-Dimensional Integral Test Assembly (PUMA) Test, Emin Fatih Ozdem

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Simulation of lC Circuits in Cylindrical Photoemission Driven Cavities using Coupled Monte Carlo and Particle-in-Cell Codes, Ravi Sanjay Shastri

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Computational Fluid Dynamics Analysis of Thermal-Hydraulic Phenomena in Nuclear Reactor Systems, Mehedi Hasan Tusar

Theses from 2022

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Modeling the reactor time-dependent delayed particle tail with Monte Carlo N-Particle (MCNP) version 6.2, Eli James Boland

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Particle swarm optimization for critical experiment design, Cole Michael Kostelac

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Characterization of cermet fuel for nuclear thermal propulsion (NTP), James Floyd Mudd

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Feasibility of a critical experiment utilizing uranium dioxide-beryllium oxide with neutron spectrum shifting capabilities, Ashley Rachel Raster

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Validation of ATHLET-CD with CORA-28 test, Murat Tuter

Theses from 2021

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Development of complex lattice cell in benchmark model of particle bed critical system, Elijah Chamberlain Lutz

Theses from 2020

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Analysis of energy economy in muon catalyzed fusion considering external x-ray reactivation, Nishant Raghav Pillai

Theses from 2018

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Development and Monte Carlo validation of a finite element reactor analysis framework, Wayne J. Brewster

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An investigation into the effects of ion tracks on α-quartz, Bryant Alan Kanies

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Fuel burnup simulation and analysis of the Missouri S&T Reactor, Joshua Hinkle Rhodes

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Modulated photothermal radiometry: Detector sensitivity study and experimental setup, Jessica Nicole Seals

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Customized multi-group cross section generation with NJOY for discrete ordinates computed tomography and radiography simulation, Steven Michael Wagstaff

Theses from 2017

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The viability of ADVANTG deterministic method for synthetic radiography generation, Andrew Albert Bingham

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Design and analysis of a passive heat removal system for a small modular reactor using STAR CCM+, Raymond Michael Fanning

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A study of the potential applications of AM241, and determining the feasibility of using Gamma spectroscopy for future physical validation, Eric A. Feissle

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Comparison of ²⁵²Cf time correlated induced fission with AmLi induced fission on fresh MTR research reactor fuel, Jay Prakash Joshi

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CFD validation and scaling of condensation heat transfer, Varun Kalra

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Analysis and implementation of accident tolerant nuclear fuels, Benjamin Joseph Prewitt

Theses from 2016

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Attenuation properties of cement composites: Experimental measurements and Monte Carlo calculations, Raul Florez

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Synthesis of Radioactive Nanostructures in a Research Nuclear Reactor, Maria Camila Garcia Toro

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Deterministic simulation of thermal neutron radiography and tomography, Rajarshi Pal Chowdhury

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Thermal characterization of phase change materials for thermal energy storage, Rami Mohammad Reda Saeed

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A feasibility study of a nuclear power plant with no moving parts, Jonathan Mark Schattke

Theses from 2015

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Impact of configuration variations on small modular reactor core performance, William Kirby Compton

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Neutronic analysis of light water Small Modular Reactor with flexible fuel configurations, Brendan Dsouza

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Computer aided detection of oral lesions on CT images, Shaikat Mahmood Galib

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Initial fuel possibilities for the Thorium Molten Salt Reactor, Dustin Gage Green

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Computer aided diagnosis of oral cancer: Using time-step CT images, Jonathan T. Scott

Theses from 2014

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Experimental investigation of the pebble bed structure by using gamma ray tomography, Fadha Shakir Ahmed

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Feasibility study of a two-fluid small modular molten salt reactor with in core heat removal capability, Brandon James Lahmann

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Determination of minor and trace elements concentration in kidney stones using elemental analysis techniques, Anjali Srivastava

Theses from 2013

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Insufficient CT data reconstruction based on directional total variation (DTV) regularized maximum likelihood expectation maximization (MLEM) method, Fahima Fahmida Islam

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A new approach to nuclear safeguard enhancement through radionuclide profiling, Aaron Dawon Peterson

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CFD simulation of void flow in ECCS, Lifeng Wang

Theses from 2012

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Wavelet based contrast limited histogram equalization for contrast enhancement of digital mammography, Ashish Vighnahar Avachat

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Hot channel determination and burnup analysis of Missouri University of Science and Technology Research Nuclear Reactor, Kelly Christopher Rogers O'Bryant

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Determination of linear attenuation coefficients of chemically bonded phosphate ceramics, Jason Joseph Pleitt

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Verification of a Monte Carlo model of the Missouri S&T reactor, Brad Paul Richardson

Theses from 2011

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Contrast enhancement of digital mammography based on multi-scale analysis, Muhammad Imran Khan Abir

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Simulation of the field electron emission characteristics of a flat panel X-ray source, Chrystian Mauricio Posada Arbeláez

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Production and characterization of supported palladium nanoparticles on multiwalled carbon nanotubes by gamma irradiation, Jessika Viviana Rojas Marin

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Density determination of tristructural-isotropic nuclear fuel using multiple projection x-ray radiography, Frank Angelo Strantz

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Upgrade and simulation of the subcritical assembly at Missouri University of Science and Technology, Lucas Powelson Tucker

Theses from 2010

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Internet-accessible hot cell with gamma spectroscopy at the Missouri University of Science and Technology research nuclear reactor, Edwin Grant

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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

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Analogy based modeling of natural convection, Vaibhav Khane

Theses from 2008

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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

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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

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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

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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

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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

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DUPoly radiation shielding effectiveness, Scott Patrick Rutenkroger

Theses from 2000

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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

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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

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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

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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

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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

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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

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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