Index Catalog // ScholarsArchive@OSU

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

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

Experimental simulations of a rotating bubble membrane radiator for space nuclear power systems

Creator:: Al-Baroudi, Homan Mohammed-Zahid
Abstract:: A rotating, flat plate condensation experiment has been developed to investigate the heat of the Rotating Bubble Membrane Radiator (RBMR). The RBMR is a proposed heat rejection system for space applications which uses working fluid condensation on the inside surface of a rotating sphere to reject heat to space. The...
Resource Type:: Dissertation
Full Text:: Approved: Andrew C.' Klein A rotating, flat plate condensation experiment has been developed to

Radiation dosimetry of radioimmunotherapy antibodies conjugated with ⁹⁰Y

Creator:: Al-Hussan, Khalid A.I. Eleissa
Resource Type:: Dissertation
Full Text:: Radioimmunotherapy Antibodies Conjugated with 90Y Abstract approved: Andrew Klein The ultimate objective of

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

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

Critical heat flux estimation for annular channel geometry

Creator:: Pagh, Richard T.
Abstract:: Critical Heat Flux (CHF) is an important safety parameter for the design of nuclear reactors. The most commonly used predictive tool for determination of CHF is a look-up table developed using tube data with an average hydraulic test diameter of 8 mm. There exist in the world today nuclear reactors...
Resource Type:: Dissertation
Full Text:: . Abstract approved: Andrew C. Klein Critical Heat Flux (CHF) is an important safety parameter for the

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

Creator:: Riley, Thomas H.
Abstract:: The goal of this project was to pave the way for more data-driven decision making when considering safety within Nuclear Engineering by proving the concept of new and innovative accident scenario modeling techniques for the analysis of the economics of nuclear safety margins. To do this, a simple, if extremely...
Resource Type:: Dissertation
Full Text:: : Andrew C. Klein The goal of this project was to pave the way for more data-driven decision making when

ScholarsArchive@OSU

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

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

Experimental simulations of a rotating bubble membrane radiator for space nuclear power systems

Radiation dosimetry of radioimmunotherapy antibodies conjugated with ⁹⁰Y

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

Fission Gas Bubble Behavior in Uranium Carbide

Critical heat flux estimation for annular channel geometry

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

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