Index Catalog // ScholarsArchive@OSU

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

Creator:: Weiss, Aaron W.
Abstract:: A large, multi-year experimental program has been conducted to develop a strain gaging program for application to the flow testing of prototypic, plate-type fuel for high performance research reactors. This test program has resulted in the selection of appropriate strain gage construction, adhesives, and protective coatings to allow the acquisition...
Resource Type:: Masters Thesis
Full Text:: converted to LEU fuel as of February, 2011 according to the National Nuclear Security Administration (2011

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

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

An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel

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

Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF

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:: for the degree of Master of Science in Nuclear Engineering presented on October 26, 2016. Title

Characterization of Oxide Growth of Aluminum Alloy 6061 for Nuclear Research and Test Reactors

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 Research AN ABSTRACT OF THE THESIS OF Youran Wei for the degree of

Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

Creator:: Peguero, Lara M.
Abstract:: Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of Nuclear Physics in Uzbekistan. The WWR-SM is a high-power, pool-type research reactor currently utilizing IRT-4M fuel made by a single Russian supplier. A candidate for...
Resource Type:: Masters Thesis
Full Text:: of Master of Science in Nuclear Engineering presented on June 6, 2016. Title: Feasibility Study of

Predicting Thermal Conductivity in Nuclear Fuels using Rattlesnake-Based Deterministic Phonon Transport Simulations

Creator:: Harter, Jackson R.
Abstract:: The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF) formulation is applied to simulate phonon transport. The neutron transport code Rattlesnake is leveraged in this fashion, slightly modi ed to accept input from variables consistent with phonon transport simulations. Several benchmark problems are modeled to assess the potential...
Resource Type:: Masters Thesis

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

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:: degree of Master of Science in Nuclear Engineering presented on October 2, 2015. Title: Steady State

An Approach to Modeling Fuel Plate Deformations in Fluid-Structure Interactions

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

ScholarsArchive@OSU

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

An Active Interrogation Technique Based on Photofission for Non-destructive Assay of Used Nuclear Fuel

Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF

Characterization of Oxide Growth of Aluminum Alloy 6061 for Nuclear Research and Test Reactors

Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

Predicting Thermal Conductivity in Nuclear Fuels using Rattlesnake-Based Deterministic Phonon Transport Simulations

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

An Approach to Modeling Fuel Plate Deformations in Fluid-Structure Interactions

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