Index Catalog // ScholarsArchive@OSU

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:: _____________________________________________________________________ Head of the School of Nuclear Science and Engineering

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:: nuclear challenges through transformative science and technology solutions.” (US Department of Energy

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:: Head of the School of Nuclear Science and Engineering Dean of the Graduate School

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:: APPROVED: Major Professor, representing Nuclear Engineering Head of the School of Nuclear Science and

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:: the experiences with light water reactors technology in the nuclear industry and the navy

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:: between Warsaw University of Technology and Oregon State University would not take place without the

High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

Creator:: Woods, Douglas N.
Abstract:: The high-order finite element S[subscript N] transport equations are solved on several test problems to investigate the behavior of the discretization method on meshes with curved edges in X-Y geometry. Simpler problems ensured the correct implementation of MFEM, the general fi nite element library employed. A convergence study using the...
Resource Type:: Masters Thesis
Full Text:: Nuclear Science and Engineering Dean of the Graduate School I understand that my thesis will become part

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

Creator:: Woods, Douglas N.
Abstract:: We spatially discretize the Sn transport equation using the high-order (HO) discontinuous finite element method (DFEM) on HO meshes. Previous work provided a proof-of-concept for this spatial discretization method in X-Y geometry. Included in the present work, we derive a spatial discretization for the Sn transport equation in both X-Y...
Resource Type:: Dissertation
Full Text:: Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

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:: Professor, representing Nuclear Engineering Head of the School of Nuclear Science and

ScholarsArchive@OSU

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

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

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

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

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

High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

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

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