Index Catalog // ScholarsArchive@OSU

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

Feasibility Study on MHD Energy Conversion for Applications in Liquid Metal Cooled Nuclear Reactors

Creator:: Qiu, Hanrui
Abstract:: The application of two-phase magnetohydrodynamic(MHD) in liquid metal cooled nuclear reactors presents opportunities to simplify the power generation system by eliminating moving components like a turbine for enhanced safety. The proposed system in this thesis consists of two loops with immiscible working ﬂuids. The compressed gas expands in the two-phase...
Resource Type:: Masters Thesis

Dynamic Probabilistic Risk Assessment Using ADAPT/RELAP5-3D for Cybersecurity Threat Analysis

Creator:: Wiltbank, Nathan E.
Abstract:: There is a growing need for an expanded Probabilistic Risk Assessment (PRA) framework that is able to accommodate new uncertainties that are present in Generation 3+ reactor designs. Dynamic PRA (DPRA) can allow for a more realistic risk assessment by taking advantage of established nuclear simulation codes to drive Dynamic...
Resource Type:: Masters Thesis

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

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 Theoretical Model for Spherical Cap Bubble Geometry

Creator:: Wieland, Isaiah T.
Abstract:: The significant variation in bubble geometry, as a function of size, has fascinated scientists for hundreds of years. However, a comprehensive explanation for these observations and the underlying physics has eluded researchers. A theoretical model which describes a the relationship between forces that produce spherical cap bubble geometry has been...
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:: . G. Mignot, Dr. L. Minc and Dr. Q. Wu. for the guidance of my thesis and defense. Secondly, I

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

Heat Loss Characterization of NIST-1's Containment Vessel

Creator:: Yoshiura, Ramon K.
Abstract:: NuScale Power has designed a small modular reactor using natural circulation cooling dependent systems for both steady-state and transient operations. The NuScale Integral Test System (NIST-1) facility was built to supply test data to NuScale Power to verify and validate computer codes for the NuScale Power Mod- ule (NPM) with...
Resource Type:: Masters Thesis

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

Creator:: Thody, Austin
Abstract:: Nuclear Thermal Rocket (NTR) designs have received renewed interest due to their superior thermal efficiencies and a rehabilitated desire for space exploration. This has resulted in improved NTR fuel designs that have unique properties that require investigation and testing in order to be more safely designed and operated. Oak Ridge...
Resource Type:: Masters Thesis
Full Text:: (Dr. Brian Woods, Dr. Leah Minc, Dr. Andrew Klein and Dr. Wade Marcum) for their help. I would

ScholarsArchive@OSU

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

Feasibility Study on MHD Energy Conversion for Applications in Liquid Metal Cooled Nuclear Reactors

Dynamic Probabilistic Risk Assessment Using ADAPT/RELAP5-3D for Cybersecurity Threat Analysis

Nano-Recrystallized UO₂ Microcantilever Bending After Ion Irradiation

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

A Theoretical Model for Spherical Cap Bubble Geometry

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

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

Heat Loss Characterization of NIST-1's Containment Vessel

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

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