Index Catalog // ScholarsArchive@OSU

Two-dimensional temperature model for target materials bombarded by ion beams

Creator:: Bostick, Kent C.
Abstract:: The ion implantation process is a very precise, controllable, and reproducible method used to enhance material properties of finished components such as ball bearings. Essentially, the target material is bombarded by accelerated ions to form a thin alloyed layer in the substrate. As the ions deposit their kinetic energy in...
Resource Type:: Masters Thesis
Full Text:: Implantation to Corrosion and Wear Protection", Nuclear Instruments and Methods in Physics Research B10/11

Radiation dosimetry of radioimmunotherapy antibodies conjugated with ⁹⁰Y

Creator:: Al-Hussan, Khalid A.I. Eleissa
Resource Type:: Dissertation
Full Text:: privilege to meet and communicate with several eminent scientists in the area of radiation physics: Dr

Nuclear design analysis of low-power (1-30 KWe) space nuclear reactor systems

Creator:: Gedeon, Stephen R.
Abstract:: Preliminary nuclear design studies have been completed on ten configurations of nuclear reactors for low power (1-30 kWe) space applications utilizing thermionic energy conversion. Additional design studies have been conducted on the TRICE multimegawatt in-core thermionic reactor configuration. In each of the cases, a reactor configuration has been determined which...
Resource Type:: Masters Thesis
Full Text:: Science in Nuclear Engineering presented November 23, 1993. Title: Nuclear Design Analysis of Low-Power

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:: more comprehensive power-reactor experiments. Advances in computational speed have extended the

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:: Longmuir achieved considerable insight in understanding the methodology and physics of thermionic

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:: ABSTRACT OF THE THESIS OF Zubaida A. Gulshan for the degree of Master of Science in Nuclear Engineering

Design and testing of fabric composite heat pipes for space nuclear power applications

Creator:: Kiestler, William C.
Abstract:: Conventional stainless steel - water and ceramic fabric composite water heat pipes have been built and tested. The tests have been conducted to compare the performance characteristics between conventional and fabric composite heat pipe radiators for space nuclear power heat rejection systems. The fabric composite concept combines a strong ceramic...
Resource Type:: Masters Thesis
Full Text:: power systems, and for the continuing problem of spacecraft temperature control. In a communication to

Ultralight fabric reflux tube thermal vacuum testing

Creator:: Pauley, Keith Alan
Abstract:: Five Ultra light Fabric Reflux Tubes (UFRTs) were tested in a thermal vacuum chamber at the National Aeronautics and Space Administration's Johnson Space Center in September 1994. These test articles were design and fabricated by staff at the Pacific Northwest Laboratory, operated by Battelle Memorial Institute for the United States...
Resource Type:: Masters Thesis
Full Text:: Abstract of the Thesis of Keith A. Pau ley for the degree of Master of Science in Nuclear Engineering

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

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Creator:: Merritt, Patrick A.
Resource Type:: Masters Thesis
Full Text:: minimum the variance. Communications with the fuel manufactureiO resulted In the following table of

ScholarsArchive@OSU

Two-dimensional temperature model for target materials bombarded by ion beams

Radiation dosimetry of radioimmunotherapy antibodies conjugated with ⁹⁰Y

Nuclear design analysis of low-power (1-30 KWe) space nuclear reactor systems

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

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

Fabric composite radiation heat transfer study

Design and testing of fabric composite heat pipes for space nuclear power applications

Ultralight fabric reflux tube thermal vacuum testing

An investigation of fabric composite heat pipe feasibility issues

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

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