Index Catalog // ScholarsArchive@OSU

Creator:: Latimer, Griffen D.
Abstract:: Current research on the topic of advanced reactor fuel types include the use of ultrahigh density Uranium-Molybdenum fuels, towards their use in high-performance research reactors. These reactors operate with high power densities, and the increased cooling requirements therefore place high relevance on the fluid-structure interaction with these fuel elements; therefore...
Resource Type:: Masters Thesis
Full Text:: elements during flow testing performed on the hydro-mechanical fuel test facility (HMFTF) at Oregon State

Creator:: Clark, R. G. (Robert Gilder), 1917-2005
Resource Type:: Masters Thesis
Full Text:: probe is to be used ln the Fuel Element Examina- tion Faciltty of the Hanford Laboratorj-es of General

Creator:: Jensen, Philip
Abstract:: The Oregon State University (OSU), Hydro Mechanical Fuel test Facility (HMFTF) is designed to hydro-mechanically test prototypical plate type fuel. OSU's fuel test program is a part of the Global Threat Reduction Initiative (GTRI), formerly known as the Reduced Enrichment for Research and Test Reactor program. One of the GTRI's...
Resource Type:: Masters Thesis
Full Text:: enriched uranium (HEU) to a low enriched uranium (LEU) fuel in an effort to reduce nuclear proliferation

Creator:: Wen, Xianfei
Abstract:: High-energy delayed γ-rays from photofission were demonstrated to be signatures for detection and identification of special nuclear materials. Such γ-rays were measured in between linac pulses using independent data acquisition systems. A list-mode system was developed to measure low-energy delayed γ-rays after irradiation. Photofission product yields of ²³⁸U and ²³⁹Pu...
Resource Type:: Dissertation
Full Text:: address the high-rate challenge in used nuclear fuel assay based on photofission technique. First, a

Creator:: Dickinson, Jeffrey Wade
Resource Type:: Masters Thesis
Full Text:: (TFE). The code developed, given the name MC11.E (for multicell thermionic fuel element), is a steady

Creator:: Howard, Trevor
Abstract:: As computational power increases, so does the desire to use fluid-structure interaction (FSI) software to design complex systems and components such as fuel plates. Presently, an effort is underway to support the design and qualification of a new nuclear fuel material which is intended for applications in select, plate-type, research...
Resource Type:: Masters Thesis
Full Text:: Nuclear Engineering presented on April 24, 2015. Title: An Approach to Modeling Fuel Plate

Creator:: Wei, Youran
Abstract:: Oxide growth is a common phenomenon on aluminum alloy cladding surfaces in nuclear research and test reactors. Without better understanding of oxide growth, excessive oxide build up on the cladding surface reduces heat transfer capability from fuel to coolant and causes safety concerns due to the potential cladding rupture or...
Resource Type:: Masters Thesis
Full Text:: nuclear reactors in order to perform accelerated experiments. Accelerated testing may enhance the

Creator:: Alberti, Anthony L.
Abstract:: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
Resource Type:: Masters Thesis
Full Text:: - ment of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels

ScholarsArchive@OSU