Index Catalog // ScholarsArchive@OSU

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:: . Almarshad ACKNOWLEDGEMENT I am deeply grateful to my advisor, Dr. Andrew C. Klein for his advice

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

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:: the completion of this project. I would like to thank Dr. Andrew Klein for being a great advisor

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:: . Third, I would like to express my gratitude to my "boss", Dr. Andrew C. Klein who deserves credit for

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Creator:: Abdul-hamid, Shahab A.
Abstract:: Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...
Resource Type:: Masters Thesis
Full Text:: I wish to thank Dr. Andrew C. Klein, my major professor and advisor, who contributed significantly

Fabric composite radiation heat transfer study

Creator:: Gulshan, Zubaida A.
Abstract:: A Fabric Composite Radiation Heat Transfer Study has been conducted to determine the effective emissivities of specific fabric composite materials. The weave of the fabric and the high strength capability of the individual fiber in combination with the thermal conductivity and chemical stability of specific metallic liner, result in a...
Resource Type:: Masters Thesis
Full Text:: U.S. Department of Energy, Grant Number DE-FG07-89ER12901. I wish to thank Dr. Andrew C. Klein for

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:: of the more significant contributors to whom I am in debt: to Dr. Andrew C. Klein, my major advisor

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

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:: did for me, I dedicate this thesis. To my major professor, Dr. Andrew C. Klein, I wish to thank him

ScholarsArchive@OSU

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

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

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

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

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Fabric composite radiation heat transfer study

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

Computer modeling and analysis of single and multicell thermionic fuel elements

Critical heat flux estimation for annular channel geometry

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

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