Although young in its existence, graphene has already shown many potential uses in nuclear engineering. Graphene has unique electrical, mechanical and optical properties that give it unmatched potential for applications raging from sensors to composites. Before these applications can be fully developed, the response to neutron and gamma irradiation must be understood. In this study, graphene grown from chemical vapor deposition was irradiated by the High Flux Isotope Reactor at Oak Ridge National Laboratory and characterized using Raman spectroscopy. It was found that the amount of structural damage was minimal, but that the graphene was doped reversibly with H₂0₂ and irreversibly. The irreversible doping is a type of soft etching process related to the exposure to O₂ as well as ionizations and heating caused by irradiation. The reversible doping is related to the products generated through the radiolysis of the water trapped between the sample and the substrate. By removing the water through evaporation the dopants related to the radiolysis products were found to be removed as well. These results are promising as they show that graphene is resilient and sensitive to the effects of irradiation simultaneously. / Master of Science

Thesis (Ph. D.)--University of Missouri-Columbia, 2000. / Typescript. Vita. Includes bibliographical references (leaves 112-118). Also available on the Internet.

Thesis (Ph. D.)--University of Missouri-Columbia, 2007. / The entire dissertation/thesis text is included in the research.pdf file; the official abstract appears in the short.pdf file (which also appears in the research.pdf); a non-technical general description, or public abstract, appears in the public.pdf file. Title from title screen of research.pdf file (viewed on March 11, 2008) Includes bibliographical references.

Thesis (Ph. D.)--University of Missouri-Columbia, 2000. / Typescript. Vita. Includes bibliographical references (leaves 112-118). Also available on the Internet.

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The purpose of this investigation was to observe the excited states of the Cs¹³³ nucleus when neutrons are inelastically scattered from the nucleus.

No description available.

Assuming an epithermal neutron flux distribution function of the form Φ'epi(E) α 1/E¹⁺ᵅ, the epithermal flux-shape parameter, alpha, and the integrated subcadmium to epicadmium flux ratio, f, were experimentally determined for two irradiation facilities in the University of Arizona TRIGA Mark I reactor. Two equivalent approaches: the Multimonitor method and the Non-linear least-squares method, based on integral (reaction rate) techniques applied to thin foils of gold, zirconium, vanadium, dysprosium, copper, manganese and molybdenum, were used. The Non-linear least-squares approach was found superior to the Multimonitor method on the basis of smaller resulting uncertainties. The resulting parameters are: α = -.0396±.0104 and f = 16.89 ± 1.08 for the Rabbit and α = -.0296 ±.0089 and f = 19.57 ± 1.26 for the Susan, where the reported uncertainties represent one sigma values.

As disc-shaped detectors are one of the primary means of measuring the neutron density, a better solution is desirable if the error due to the depression factor is to be made negligible. In this paper, an attempt is made to solve this problem in the oblate spheroidal co-ordinate system which most nearly describes the disc-shaped detector, so that solutions may be obtained that describe depression factors for detectors of varying thicknesses and radii.