Index Catalog // ScholarsArchive@OSU

Development of a binary mixture gas composition instrument for use in a confined high temperature environment

Creator:: Cadell, Seth R.
Abstract:: With recent advancements in material science, industrial operations are being conducted at higher and higher temperatures. This is apparent in the nuclear industry where a division of the field is working to develop the High Temperature Gas Reactor and the Very High Temperature Gas Reactor concurrently. Both of these facilities...
Resource Type:: Dissertation
Full Text:: : _____________________________________________________________________ Brian G. Woods With recent advancements in material science, industrial operations are being

Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor

Creator:: Gradecka, Malwina
Abstract:: Since High Temperature Gas-cooled Reactors are being considered as most promising design of upcoming IV Gen reactors, thus key research areas were identified to address safety aspects of this design. Number of simulations and experiments need to be conducted in this field. In this study thermal-hydraulics aspects of coolant flow...
Resource Type:: Dissertation
Full Text:: : _____________________________________________________ Brian G. Woods Piotr Furmański Since High Temperature Gas-cooled

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:: Brian Woods Sodium cooled nuclear reactors are being considered for the next generation of nuclear

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:: Using VIPRE-01 and FRAPCON-3 Abstract approved: Brian G. Woods The Multi

Development of a Novel MEMS Thermal Sensor Array for Pebble Bed HTGRs

Creator:: Hertel, Matthew A.
Abstract:: A novel high temperature thermal instrument is proposed, which utilizes a dual-sensing platinum resistor encased in a mono-crystalline alpha-alumina (sapphire) substrate. The instrument is comprised of four platinum trace elements, oriented with 90° rotational symmetry atop a 1120 oriented crystal lattice substrate. All four of these sensors measure temperature directly...
Resource Type:: Dissertation
Full Text:: : ________________________________________________________ Brian G. Woods A novel high temperature thermal instrument is proposed, which utilizes a

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:: : ______________________________________________________ Brian Woods Among the candidates for the next generation of nuclear power plant is the high

Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

Creator:: Gullekson, Brian J.
Abstract:: Partitioning of trivalent actinides (in particular, americium and curium) from the fission produced light lanthanides is a major concern of used nuclear fuel reprocessing for the purposes of waste disposal. Several solvent extraction processes have been developed to address these chemically difficult separations. The historically employed TALSPEAK Process utilizes di-2-ethylhexyl...
Resource Type:: Dissertation
Full Text:: AN ABSTRACT OF THE DISSERTATION OF Brian J

Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor

Creator:: Gutowska, Izabela
Abstract:: To understand how a Depressurized Loss of Forced Convection (D-LOFC) initiated from a double-ended guillotine break may affect further operation of a High Temperature Gas Cooled Rector (HTGR), thorough understanding of each specific stage of this event is required. Key considerations that need to be determined is the amount of...
Resource Type:: Dissertation
Full Text:: : ______________________________________________________ Brian G. Woods Piotr Furmanski To understand how a Depressurized Loss

Archaeological Textile Fragments Present an Opportunity In the Study of Social and Landscape Interactions

Creator:: Lopez, Kirsten M.
Abstract:: Textiles (including basketry, cordage, woven, knotted, or plaited products) make up a considerable portion of the perishable archaeological record in dry caves of the northern Great Basin region, much of which is created from plants and plant fibers. The archaeological study of precontact textiles greatly informs our understanding of how...
Resource Type:: Masters Thesis
Full Text:: support allowed the analysis possible: Jesse Muriatli, Chris Russo, Alyssa Shiel, Brian Haley, and

On the mechanism transition of power transient critical heat flux

Creator:: Yan, Yikuan
Abstract:: The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
Resource Type:: Dissertation
Full Text:: committee members: Dr. Qiao Wu Dr. Brian Fronk, Dr. Brian Woods. and the GCR Dr. Leah Minc. I would

ScholarsArchive@OSU

Development of a binary mixture gas composition instrument for use in a confined high temperature environment

Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

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

Development of a Novel MEMS Thermal Sensor Array for Pebble Bed HTGRs

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

Organic Phase Inter-Ligand and Metal-Ligand Speciation in TALSPEAK and ALSEP Solvent Extraction Systems

Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor

Archaeological Textile Fragments Present an Opportunity In the Study of Social and Landscape Interactions

On the mechanism transition of power transient critical heat flux

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