Index Catalog // ScholarsArchive@OSU

Benchmark comparison of the Oregon State TRIGA reactor between MCNP6 and Serpent 2

Creator:: Law, Tyler
Abstract:: A model of the Oregon State TRIGA reactor was developed in Serpent 2 by translating a previously accepted MCNP model. Both models were verified and validated via comparison of each model and data gathered from the core start-up. Reactivity bias in each code was determined. Using the rod drop method,...
Resource Type:: Masters Thesis

CFD Verification, Validation, and Sensitivity Study of Internally Heated Concentric Tube Thermosyphon O-SERTTA

Creator:: Miller, Jaden
Abstract:: Irradiation experiments are a critical aspect of the nuclear fuels and materials qualification process. Determining the flow conditions of these experiments is necessary for understanding response of nuclear components during transient and normal operation. Quality flow data is lacking for cartridge-type irradiation experiments with annular flow natural circulation designs. Data...
Resource Type:: Masters Thesis
Full Text:: Howard, Dr. Guillaume Mignot, and Aaron Weiss. Appreciation is also extended to the Graduate Council

Thermal Stability of Advanced Metallic Nuclear Fuel Microstructures

Creator:: Wright, Alexander A.
Abstract:: Metallic nuclear fuels have long been studied for use in advanced nuclear reactors, with efforts invested in improving the viability of metallic nuclear fuel elements and overall safety of advanced reactor design concepts. During reactor operations, fuel forms undergo restructuring due to a variety of physical phenomena. Expansion of the...
Resource Type:: Masters Thesis
Full Text:: Meyer, Dr. Guillaume Mignot, and Aaron Weiss for their time and invaluable efforts assisting me

Quantifying System Similarity Between EBR-II and the VTR Integral Test Facility Through Hierarchical Two-Tiered Scaling and RELAP5 Simulations

Creator:: Leitherer, Brett C.
Abstract:: Advanced reactor designs offer many advantages over typical Light Water Reactors (LWRs) including fast neutron capability, passive safety features, and improved performance. While the future for these reactors seems promising, operating and test experience is necessary to further validate such claims. The development of full-scale facilities has proved to be...
Resource Type:: Masters Thesis

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

A Computational Fluid Dynamic Study on Flow Induced Vibration in Helically Wire Wrapped Rods Under Axial Turbulent Flow

Creator:: Winkle, Tristan
Abstract:: Vibration of nuclear fuel rods is an area of significance for the long-term safe operation of any nuclear power plant. One mechanism of vibration, flow induced vibration (FIV), must be quantified when designing a new core, such as a sodium fast reactor which employs helically-wrapped wire spacers. Experimental work undertaken...
Resource Type:: Masters Thesis
Full Text:: advice and software support. Dr. Guillaume Mignot provided me with the tools and knowledge to produce a

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:: . G. Mignot, Dr. L. Minc and Dr. Q. Wu. for the guidance of my thesis and defense. Secondly, I

A Computational Fluid Dynamics Study on the Hydrodynamics for Tandem Plate Configurations under Turbulent Flow

Creator:: Gjemso, Jonathan
Abstract:: The subject of fluid-structure interactions (FSI) are a matter concerning the design of any element immersed in a fluid. One of the most critical phenomena embedded within the scope of FSI is the creation of vortex-induced vibrations (VIV). These type of vibrations originate in a given body as a result...
Resource Type:: Masters Thesis
Full Text:: project. I would also like to thank the additional members of my graduate committee: Dr. G. Mignot, Dr

Quantifying System Distortions between the VTR and IVTR facilities through H2TS Scaling Methodology and RELAP5-3D Simulations

Creator:: Johnson, Juwan A.
Abstract:: Sodium Cooled Fast Reactors (SFR) are complex and expensive due to high operating temperatures and neutron flux which pose technical challenges for these reactors. To overcome these challenges with SFRs, research and development of small scale and large-scale facilities are needed to bridge the gap in understanding. Scaling analyses develop...
Resource Type:: Masters Thesis
Full Text:: been possible. I would like to thank Dr. Guillaume Mignot for his guidance with my thesis and

High Fidelity 3-Omega Probe Installation and Verification in a Scanning Electron Microscope

Creator:: Powers, Robert D.
Abstract:: There are efforts underway at Idaho National Laboratory to design, modify, and implement an array of techniques into a nuclear material ready Scanning Electron Microscope (SEM) to accelerate comprehensive characterization of the physical properties and microstructures of irradiated fuels and materials. The goals of adding a micro four-point probe (M4PP)...
Resource Type:: Masters Thesis
Full Text:: . Additionally, I would like to thank Dr. Guillaume Mignot for his guidance with my thesis and presentation in

ScholarsArchive@OSU

Benchmark comparison of the Oregon State TRIGA reactor between MCNP6 and Serpent 2

CFD Verification, Validation, and Sensitivity Study of Internally Heated Concentric Tube Thermosyphon O-SERTTA

Thermal Stability of Advanced Metallic Nuclear Fuel Microstructures

Quantifying System Similarity Between EBR-II and the VTR Integral Test Facility Through Hierarchical Two-Tiered Scaling and RELAP5 Simulations

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

A Computational Fluid Dynamic Study on Flow Induced Vibration in Helically Wire Wrapped Rods Under Axial Turbulent Flow

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

A Computational Fluid Dynamics Study on the Hydrodynamics for Tandem Plate Configurations under Turbulent Flow

Quantifying System Distortions between the VTR and IVTR facilities through H2TS Scaling Methodology and RELAP5-3D Simulations

High Fidelity 3-Omega Probe Installation and Verification in a Scanning Electron Microscope

Limit your search

Academic Affiliation

Advisor

Commencement Year

Committee Member

Creator

Contributor

Date

Decade

Degree Field

Degree Level

Degree Name

Language

License

Peer Reviewed

Resource Type

Rights Statement

Subject

Search Constraints

Search Results

Limit your search