Index Catalog // ScholarsArchive@OSU

Capabilities of Detecting Medical Isotope Facilities through Radioxenon Sampling

Creator:: MacDougall, Matthew R.
Abstract:: Medical Isotopes are a necessity in modern medicine for cancer treatments and medical imaging. In order to ensure that the needs and demands are met for the medical procedures, facilities are put in place to produce these isotopes. There are over 25 different isotopes of interest being produced by more...
Resource Type:: Masters Thesis
Full Text:: : ______________________________________________________ Andrew C. Klein Medical Isotopes are a necessity in modern medicine for cancer treatments

Nuclear investigations of the eletrolysis of D₂O using palladium cathodes and platinum anodes

Creator:: Zahm, Lance Leon
Resource Type:: Masters Thesis
Full Text:: come to pass. My sincere appreciation goes out to Dr. Andrew C. Klein, Dr. Alan Robinson, Dr. Jose

Preliminary framework for the run-ahead predictive simulation software (RAPSS)

Creator:: Makinson, Kevin A.
Abstract:: The Run-Ahead Predictive Simulation Software (RAPSS) is an architecture designed for faster-than-real-time decision support for operators of complex networks. To enable further development of the RAPSS methodology, the necessary proof of principle is illustrated in two applications: decision support for shift technical advisors in nuclear power plant control rooms (RAPSS-STA),...
Resource Type:: Dissertation
Full Text:: approved: ________________________________________________________________________ Andrew C. Klein

Computer modeling and analysis of single and multicell thermionic fuel elements

Creator:: Dickinson, Jeffrey Wade
Resource Type:: Masters Thesis
Full Text:: Modeling and Analysis of Single and Multicell Thermionic Fuel Elements Abstract Approved: Andrew C. Klein

An investigation of fabric composite heat pipe feasibility issues

Creator:: Marks, Timothy S.
Abstract:: The design of a fabric composite heat pipe has been completed. It is composed of two end caps, between which a fluid containment liner composed of metal foil and an outer structural layer composed of a ceramic fabric is stretched. The interior of the heat pipe is layered with a...
Resource Type:: Masters Thesis
Full Text:: Issues AN ABSTRACT OF THE THESIS OF Timothy S. Marks for the degree of Master of Science in Nuclear

An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

Creator:: Onufer, Mark
Abstract:: The International Handbook of Evaluated Reactor Physics Benchmark Experiments contains detailed descriptions of many different reactor facilities. A large portion of these experiments have not been fully modeled due to the unavailability of computational power at the time of the experiment’s execution. With the advent of renewed interest in Sodium...
Resource Type:: Masters Thesis
Full Text:: :__________________________________________________ Andrew C. Klein The International Handbook of Evaluated Reactor Physics Benchmark

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

Creator:: Al-Kheliewi, Abdullah S.
Abstract:: A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...
Resource Type:: Dissertation
Full Text:: fuel element for nuclear space reactors AN ABSTRACT OF THE THESIS OF Abdullah S. A1- Kheliewi for

Fission Gas Bubble Behavior in Uranium Carbide

Creator:: Matthews, Christopher
Abstract:: The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution...
Resource Type:: Dissertation
Full Text:: : Fission Gas Bubble Behavior in Uranium Carbide Abstract approved: Andrew C. Klein The need for cheap

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Creator:: Lenhof, Renae
Abstract:: A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...
Resource Type:: Masters Thesis
Full Text:: : ______________________________________________________ Andrew C. Klein A limited scope Probabilistic Risk Assessment (PRA) of a vented

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

Creator:: Thody, Austin
Abstract:: Nuclear Thermal Rocket (NTR) designs have received renewed interest due to their superior thermal efficiencies and a rehabilitated desire for space exploration. This has resulted in improved NTR fuel designs that have unique properties that require investigation and testing in order to be more safely designed and operated. Oak Ridge...
Resource Type:: Masters Thesis
Full Text:: approved: ______________________________________________________ Andrew C. Klein Nuclear

ScholarsArchive@OSU

Capabilities of Detecting Medical Isotope Facilities through Radioxenon Sampling

Nuclear investigations of the eletrolysis of D₂O using palladium cathodes and platinum anodes

Preliminary framework for the run-ahead predictive simulation software (RAPSS)

Computer modeling and analysis of single and multicell thermionic fuel elements

An investigation of fabric composite heat pipe feasibility issues

An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

Fission Gas Bubble Behavior in Uranium Carbide

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

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