Accelerator Facility Shielding Design, 2015 University of Tennessee - Knoxville
Accelerator Facility Shielding Design, Kaitlyn Hope Darby, Tucker Caden Mcclanaha, Adrian Moore, Christopher Tyler Crutcher, Melissa Alexis Megonigal
University of Tennessee Honors Thesis Projects
No abstract provided.
Hybrid K-Edge Densitometry As A Method For Materials Accountancy Measurements In Pyrochemical Reprocessing, 2015 University of Tennessee - Knoxville
Hybrid K-Edge Densitometry As A Method For Materials Accountancy Measurements In Pyrochemical Reprocessing, Matthew Tyler Cook
Pyrochemical reprocessing is a proven method to recover useful fissile material from spent nuclear fuel. The process requires high temperatures and an inert atmosphere thus complicating the prospect of making materials accountancy measurements. Development of a measurement method for materials accountancy measurements has become necessary since pyroprocessing is receiving more attention as a possible compliment to aqueous reprocessing methods. If pyroprocessing is to be adapted from the engineering scale to a commercially viable reprocessing method a comprehensive safeguards measurement method and strategy must be developed.
Hybrid k-edge densitometry (HKED) has been applied to aqueous reprocessing measurements in commercial facilities. This ...
Molecular Dynamics Simulation Of Irradiation Damage In Multicomponent Alloys, 2015 University of Tennessee - Knoxville
Molecular Dynamics Simulation Of Irradiation Damage In Multicomponent Alloys, Wei Guo
The development of the generation IV reactors calls for radiation resistant materials. This thesis proposes that the newly developed single phase solid solution of high-entropy alloys (HEAs) can be such candidates. HEAs can undergo the crystalline to amorphous to crystalline (C-A-C) transitions under radiation. The radiation induced amorphous structure is a highly radiation resistant medium as shown by previous studies, and it further transforms to crystalline phases without much structural defects. In this thesis, by reviewing the formation rules of solid solutions and amorphous metallic glasses, it is suggested that the atomic size plays a key role affecting the C-A-C ...
Evaluation, Construction, And Verification Of A Subchannel Steady State Heat Transfer Code For Plate-Fueled Reactors, 2015 University of Tennessee - Knoxville
Evaluation, Construction, And Verification Of A Subchannel Steady State Heat Transfer Code For Plate-Fueled Reactors, Cory Landon Griffard
Several high performance research reactors use plate fuel that is clad with aluminum and cooled with forced convection of subcooled water. High resolution multiphysics simulation tools have been developed to allow the performance of the core in these reactors to be assessed in more detail. The high resolution multiphysics (HRMP) simulation tools must go through verification and validation (V&V) to ensure the additional detail of the outcomes is accompanied with quantifiable uncertainties and confidence intervals. As an example of V&V, a one-dimensional subchannel code with conventional engineering flow and heat transfer models may be used to check the ...
Electronic Energy Loss Of Heavy Ions And Its Effects In Ceramics, 2015 University of Tennessee - Knoxville
Electronic Energy Loss Of Heavy Ions And Its Effects In Ceramics, Ke Jin
Energy loss of medium energy heavy ions (i.e. Cl, Br, I, and Au) in thin compound foils containing light elements (i.e. silicon carbide and silicon dioxide) is directly measured using a time-of-flight elastic recoil detection analysis (ToF-ERDA) technique. An improved data analysis procedure is proposed to provide the experimentally determined electronic stopping powers. This analysis procedure requires reliable predictions of nuclear stopping. Thus, the nuclear stopping predicted by the Stopping and Range of Ions in Matter (SRIM) code is validated by measuring the angular distribution of 1 MeV Au ions after penetrating a thin silicon nitride foil, using ...
Characterization Of Mechanically Cooled High Purity Germanium (Hpge) Detectors At Elevated Temperatures, 2015 University of Tennessee - Knoxville
Characterization Of Mechanically Cooled High Purity Germanium (Hpge) Detectors At Elevated Temperatures, Joseph Benjamin Mccabe
High resolution gamma spectroscopy is a tool used in nuclear security applications due to its achievable energy resolution and associated ability to identify special nuclear material. This identification ability is achieved by identifying the characteristic gamma-rays of a material. The challenges that have confronted industry concerning the use of hand-held high purity germanium (HPGe) in homeland security applications have centered on weight, geometry, and cool-down time. Typical liquid nitrogen cooled detectors ranging in size from 10% to 150% detectors will cool down sufficiently within 2-6 hours of filling. The cool-down time achieved in this research ranges from 45 min on ...
Dynamic Modeling Of A Small Modular Reactor For Control And Monitoring, 2015 University of Tennessee - Knoxville
Dynamic Modeling Of A Small Modular Reactor For Control And Monitoring, Jeffrey Robert Kapernick
A system model of the Babcock & Wilcox Generation mPower small modular reactor (SMR) was developed within the MATLAB-Simulink environment. A detailed physical configuration of this SMR was established based on the limited information available for the mPower reactor. This is an important step in the development of the simulation model. Three mathematical models were combined to simulate the control dynamics. A lumped-parameter approximation of fuel-to-coolant heat transfer is combined with vessel upper plenum and lower plenum coolant masses to represent the core power and heat transfer dynamics. A nodalized moving boundary steam generator model balances mass, momentum, and energy for ...
User Perspective And Analysis Of The Continuous-Energy Sensitivity Methods In Scale 6.2 Using Tsunami-3d, 2015 University of Tennessee - Knoxville
User Perspective And Analysis Of The Continuous-Energy Sensitivity Methods In Scale 6.2 Using Tsunami-3d, Elizabeth Lauryn Jones
The Tools for Sensitivity and UNcertainty Analysis Methodology Implementation (TSUNAMI) suite within the SCALE code system makes use of eigenvalue sensitivity coefficients to enable several capabilities, such as quantifying the data-induced uncertainty in calculated eigenvalues and assessing the similarity between different critical systems. The TSUNAMI-3D code is one tool within the TSUNAMI suite used to calculate eigenvalue sensitivity coefficients in three-dimensional models. The SCALE 6.1.2 code system includes only the multigroup (MG) mode for three-dimensional sensitivity analyses; however, the upcoming release of SCALE 6.2 will feature the first implementation of continuous-energy (CE) sensitivity methods in SCALE. For ...
Modeling Radiation-Induced Segregation In Ferritic-Martensitic Steels, 2015 University of Tennessee - Knoxville
Modeling Radiation-Induced Segregation In Ferritic-Martensitic Steels, Aaron Patrick Selby
As ferritic-martensitic (FM) steels receive increasing interest, due to the development of Generation IV fission reactors and fusion reactors, it is imperative to understand how the metals will behave under irradiation. Of the radiation effects, radiation-induced segregation (RIS) is of particular concern as it can lead to the formation of intermetallic phases, stress corrosion cracking, and other detrimental effects. However, predicting RIS in FM steels is more complex due to the lack of consistent trends in experimental results. Therefore, we developed a program to simulate RIS in FM alloys. By performing a sensitivity analysis of the input parameters, we found ...
Impact Of Fuel Rod Coatings On Reactor Performance And Safety, 2015 University of Tennessee - Knoxville
Impact Of Fuel Rod Coatings On Reactor Performance And Safety, Ian Robert Stewart
This study evaluates the use of a ceramic coating on the Zr-alloy cladding within a PWR using four ceramic compounds of 5 and 10 micron thicknesses: ZrO2, TiAlN, Ti2AlC, and Ti3AlC2. The film’s impact is assessed for variation on: reactivity, fuel cycle length, maximum temperature, film’s roughness, and transient conditions. The reactivity is analyzed using the following methods: change in the multiplication factor (k) each film introduces to the system using the ABH method, and Monte Carlo software (MCNP). Both methods are in good agreement, yielding less than half a percent change from a reference, no-film fuel pin ...
Doping Of Fluorchlorozirconate And Borate-Silica Glass Ceramics For Medical Imaging And Fast Neutron Scintillation, 2015 University of Tennessee - Knoxville
Doping Of Fluorchlorozirconate And Borate-Silica Glass Ceramics For Medical Imaging And Fast Neutron Scintillation, Julie Elizabeth Swafford
Borate silica glass ceramics were produced for neutron scintillation. The Glass ceramics were doped with europium fluoride [EuF2] and cerium chloride [CeCl3]. Isotopic lithium fluoride [6LiF] and boron oxide [10B2O3] were used in most samples while non-isotopic lithium fluoride [LiF] and boron oxide [ B2O3] were used in the rest. When exposed to a neutron beam, samples doped with europium fluoride [EuF2] scintillated while samples doped with cerium chloride [CeCl3] did not. This contradicts current literature on fast scintillation. What is even more significant is that with europium fluoride ...
Assessment Of Reactivity Equivalence For Enhanced Accident Tolerant Fuels In Light Water Reactors, 2015 University of Tennessee - Knoxville
Assessment Of Reactivity Equivalence For Enhanced Accident Tolerant Fuels In Light Water Reactors, Nathan Michael George
The neutronic behavior of accident tolerant fuel (ATF) concepts was simulated in light water reactors (LWRs) to establish design parameters to match reactivity lifetime requirements of standard UO2 [uranium dioxide]/Zircaloy fuel. The two concepts discussed in this dissertation are fully ceramic micro-encapsulated (FCM) fuel and alternate cladding concepts. To compare the required fuel alterations against standard UO2/Zircaloy fuel, a 2D lattice-physics based reactivity equivalence method was established to estimate excess reactivity at the completion of each weighted batch cycle.
In the case of FCM fuel, the uranium-based tristructural isotropic (TRISO) kernel and the surrounding particle layers ...
Citations Of Publications, 2015 Wroclaw University of Technology
Citations Of Publications, Wojciech M. Budzianowski
No abstract provided.
C.V., 2015 Wroclaw University of Technology
C.V., Wojciech M. Budzianowski
No abstract provided.
Offer For The Economy, 2015 Wroclaw University of Technology
Offer For The Economy, Wojciech M. Budzianowski
No abstract provided.
Oferta Dla Gospodarki, 2015 Wroclaw University of Technology
Oferta Dla Gospodarki, Wojciech M. Budzianowski
No abstract provided.
Inżynieria Chemiczna Lab., 2015 Wroclaw University of Technology
Inżynieria Chemiczna Lab., Wojciech M. Budzianowski
No abstract provided.
Tematyka Prac Doktorskich, 2015 Wroclaw University of Technology
Tematyka Prac Doktorskich, Wojciech M. Budzianowski
No abstract provided.
Incorporating Public Perceptions Into The Selection Of A Nuclear Fuel Cycle, 2015 Virginia Commonwealth University
Incorporating Public Perceptions Into The Selection Of A Nuclear Fuel Cycle, John M. Swanson
Theses and Dissertations
The final disposal location for used nuclear fuel in the U.S. remains unresolved. A major complication in resolving this issue has historically been the lack of public acceptance. This motivates the creation of a decision making model for selecting a nuclear fuel cycle in the U.S. that incorporates the preferences of the public. A model based on the Analytic Hierarchy Process (AHP) was created, tested, and shown to be problematic in incorporating public opinion into decision objectives. A new model based on Multi-Attribute Utility Theory (MAUT) has been created. This model contains the fundamental objectives for both technical ...
Characterization Of Lithium-6 As A Commercial Helium-3 Alternative For Nuclear Safeguards And Security, 2014 University of Tennessee - Knoxville
Characterization Of Lithium-6 As A Commercial Helium-3 Alternative For Nuclear Safeguards And Security, Alexander Martin Okowita
Helium-3 detectors are efficient, reliable neutron detectors, but their high demand has reduced their supply to a very miniscule level, making them very expensive. The goal of this project is to test and evaluate an alternative produced by industry. Current testing is being done with a Lithium Zinc Sulfide (6LiF:ZnS(Ag)) detector from Aspect used in their portal monitors.
There are three basic requirements for neutron detectors used in nuclear safeguards and security: 1) high absolute detection efficiency, 2) maintaining neutron detection efficiency when simultaneously exposed to a high gamma ray exposure rate, and 3) the ability to ...