Index Catalog // ScholarsArchive@OSU

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

Creator:: Zahm, Lance Leon
Resource Type:: Masters Thesis
Full Text:: gamma ray data show no observable quantities of traditional D-D fusion reaction products during

Top-down scaling analysis of the integral reactor vessel test facility

Creator:: Graves, Joshua D.
Abstract:: Oregon State University has conducted research in collaboration with TerraPower, LLC, to perform a top-down scaling analysis of an integrated test facility. The goal of this facility is to simulate transient and quasi-steady phenomena at a reduced scale, including steady-state operation, pump coastdown, natural circulation, reactor head heat transfer, and...
Resource Type:: Masters Thesis
Full Text:: Vessel Test Facility AN ABSTRACT OF THE THESIS OF Joshua D. Graves for the degree of Master of

Ultralite copper reflex tube life test and ceramic fabric wicking rate experiments

Creator:: Snuggerud, Ross D.
Abstract:: This thesis covers two topics. The first subject involves tests run on a ultralite reflux tube supplied by Battelle Pacific Northwest Laboratories (PNL). The second topic involves tests to determine the relative wicking rates of several different fabrics. The ultralite reflux tube supplied by PNL was constructed of copper and...
Resource Type:: Masters Thesis
Full Text:: wicking rate experiments AN ABSTRACT OF THE THESIS OF Ross D. Snuggerud for the degree of Master of

Cost-Benefit Analysis : Proposed Safety Upgrades to Currently Operating Nuclear Power Plants

Creator:: Jordahl, Jonathan T.
Abstract:: In the wake of nuclear accidents such as Three Mile Island Unit 2 and Fukushima, the nuclear power industry’s safety record is scrutinized. Today the main concerns lies with hydrogen production in a nuclear reactor core when the zirconium fuel cladding reacts with the water coolant during an accident, creating...
Resource Type:: Masters Thesis
Full Text:: : ______________________________________________________ Andrew C. Klein In the wake of nuclear accidents such as Three Mile Island Unit 2 and

Experimental Investigation of the Transition to Natural Convection in HTGR Applications using the Oregon State SFSETF

Creator:: Fishler, Joshua D.
Abstract:: High Temperature Gas Reactors (HTGRs) are positioned to disrupt local and global markets via their unique ability to produce carbon-free process heat, high efficiency power generation, and passively safe operational features. However, significant impediments still exist to delay deployment of this particular technology, including a lack of experimental data, verified...
Resource Type:: Dissertation
Full Text:: AN ABSTRACT OF THE DISSERTATION OF Joshua D. Fishler

Feasibility study on a soluble boron-free small modular reactor

Creator:: Mart, Justin R.
Abstract:: The elimination of soluble boron creates several advantages for Small Modular Reactor (SMR) operation. Most of these advantages are realized through significant core simplification (removal of pipes, pumping, and purification systems), the removal of the corrosive effects of soluble boron, and from improved safety effects. However, removing soluble boron creates...
Resource Type:: Masters Thesis
Full Text:: Andrew C. Klein The elimination of soluble boron creates several advantages for Small Modular

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

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

A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

Creator:: Almarshad, Abdullah I. A.
Abstract:: A model has been developed to predict the long-term oxidation rate of Zircaloy-4 for ex-reactor (autoclave) and in-reactor (PWR) environments and operating conditions. A computer program has been written to solve the oxygen diffusion equation by employing a fully implicit finite difference method for a one dimensional cylindrical geometry. The...
Resource Type:: Dissertation
Full Text:: : V Andrew 0: Klein A model has been developed to predict the long-term oxidation rate of Zircaloy-4

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:: Doctor of Philosophy Completed September 20, 1993 Commencement June, 1994 APPROVED: Andrew

ScholarsArchive@OSU

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

Top-down scaling analysis of the integral reactor vessel test facility

Ultralite copper reflex tube life test and ceramic fabric wicking rate experiments

Cost-Benefit Analysis : Proposed Safety Upgrades to Currently Operating Nuclear Power Plants

Experimental Investigation of the Transition to Natural Convection in HTGR Applications using the Oregon State SFSETF

Feasibility study on a soluble boron-free small modular reactor

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

Computer modeling and analysis of single and multicell thermionic fuel elements

A model for waterside oxidation of zircaloy fuel cladding in pressurized water reactors

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

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