Index Catalog // ScholarsArchive@OSU

Material Expressions of Class, Status and Authority amongst Commissioned Officers at Fort Yamhill and Fort Hoskins, Oregon, 1856-1866

Creator:: Eichelberger, Justin E.
Abstract:: During the 19th century the United States Army was a military institution characterized by a hierarchical system of authoritative, social and economic inequality between members of its different military grades. Although necessary for insuring military discipline within the Army this system of inequality also influenced the non-military social lives of...
Resource Type:: Dissertation
Full Text:: AN ABSTRACT OF THE DISSERTATION OF Justin E. Eichelberger

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Creator:: Mai, Anh T.
Abstract:: The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
Resource Type:: Masters Thesis
Full Text:: hydraulic analysis. The hot channel and hot rod results are compared with thermal design limits to

Investigation of Drag Coefficient and Virtual Mass Coefficient on Rising Ellipsoidal Bubbles

Creator:: Dueñas, Alexander M.
Abstract:: Accurately describing drag and virtual mass forces in two-phase flows is crucial for high fidelity modeling of nuclear thermal hydraulic safety systems. This study compares existing drag coefficient correlations commonly used in computational fluid dynamics (CFD) applications for air bubbles to experimental data collected for ellipsoidal air bubbles of varying...
Resource Type:: Masters Thesis
Full Text:: measured the virtual mass coefficient on a cylinder rod using a method that considers viscous and wake

Development of a Fast Spectrum Test Loop at the Advanced Test Reactor

Creator:: Higgins, Anton
Abstract:: The United States currently has no infrastructure to provide a fast neutron flux for research purposes. With the increased interest in Sodium Fast Reactor (SFR) technology, this type of infrastructure is necessary for further development of key components such as Versatile Test Reactor. The purpose of this research is to...
Resource Type:: Masters Thesis
Full Text:: outlet was reached. The fuel rod radial temperature profile was lower than was expected, likely due to

Analysis of Asymmetric Heating on a Scaled High Temperature Gas Reactor Experiment During a Pressurized Conduction Cooldown

Creator:: Moore, Thomas
Abstract:: Among the candidates for the next generation of nuclear power plant is the high temperature gas reactor (HTGR). Since the HTGR does not have the same operational history as water cooled reactors do in the United States, investigation into the response of different accident phenomena is still an active area...
Resource Type:: Dissertation
Full Text:: instrumentation such as the control rod drive shafts are located in the upper plenum. As such, it is important

Comparison of eye plaque dosimetry using deterministic and Monte Carlo methods

Creator:: Bristol, Jonathan R.
Abstract:: Eye plaque brachytherapy is an established technique for the treatment of ocular melanoma that allows for the preservation of the affected eye as well as visual function. A common treatment planning system for eye plaque procedures, Plaque Simulator (PS), assists physicists in calculating the radiation dose to the tumor and...
Resource Type:: Masters Thesis
Full Text:: Deck………………………………………………………… 86 Appendix E: MCNPX 20mm Input Deck………………………………………………………… 105

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

Creator:: Moore, Thomas M.
Abstract:: Sodium cooled nuclear reactors are being considered for the next generation of nuclear power plants to provide clean electricity to the world. To prove the safety of these reactors, the fuel must be shown to safely handle large neutron fluxes that cause a spike in the thermal output of the...
Resource Type:: Masters Thesis
Full Text:: -IIC HOP 1-6A Fuel Rod [49] .......................................................... 39 Figure 3-6

Just Beneath the Surface : Analysis of Excavations at 35WS453, The Dalles Chinatown

Creator:: French, Jamie
Abstract:: In a mostly abandoned block, capped by concrete, the building at 210 East 1st Street, The Dalles, Oregon still stands as one of three remaining structures. This building housed the Wing Hong Hai Company, a mercantile store and Chinese laundry, from 1889 to 1926. Beneath the modern concrete that encircles...
Resource Type:: Masters Thesis

A New Approach of Computational Fluid Dynamics Studying Power Transient Critical Heat Flux

Creator:: Chen, Tsung-Wen
Abstract:: Power transient boiling has been studied for decades, however, the mechanistic understanding of phenomena which occur during such an event remains incomplete. Due to a dearth of systematic researches, the information of studied phenomenon, detailed physics and applicable hypothesis are very limited. Transient critical heat flux (CHF) is paramount in...
Resource Type:: Masters Thesis
Full Text:: ....................................................38 Fig. 20. Cross view of test section with different heater rod sets

Nano-Recrystallized UO₂ Microcantilever Bending After Ion Irradiation

Creator:: Cullison, Mack
Abstract:: Idaho National Laboratories recently conducted micromechanical testing of nano-recrystallized UO₂ as a part of an ongoing investigation of High Burnup Structure (HBS). The goals of the test were to determine the fracture stress, and the elastic modulus of subdivided grains within UO₂ using ion irradiation rather than neutron irradiation to...
Resource Type:: Masters Thesis
Full Text:: rod or rectangular dog-bone specimen is prepared to pull the material to determine the yield stress

ScholarsArchive@OSU

Material Expressions of Class, Status and Authority amongst Commissioned Officers at Fort Yamhill and Fort Hoskins, Oregon, 1856-1866

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Investigation of Drag Coefficient and Virtual Mass Coefficient on Rising Ellipsoidal Bubbles

Development of a Fast Spectrum Test Loop at the Advanced Test Reactor

Analysis of Asymmetric Heating on a Scaled High Temperature Gas Reactor Experiment During a Pressurized Conduction Cooldown

Comparison of eye plaque dosimetry using deterministic and Monte Carlo methods

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

Just Beneath the Surface : Analysis of Excavations at 35WS453, The Dalles Chinatown

A New Approach of Computational Fluid Dynamics Studying Power Transient Critical Heat Flux

Nano-Recrystallized UO₂ Microcantilever Bending After Ion Irradiation

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