Index Catalog // ScholarsArchive@OSU

Advancing the understanding of bulk metallic glasses as structural materials through exploration of mechanical properties

Creator:: Naleway, Steven E.
Abstract:: Bulk metallic glasses (BMGs) offer a great deal of potential through their near-theoretical strength, potentially high toughness and unique forming and molding traits. However, there are still a number of outstanding issues that bar their widespread use. This thesis describes the investigation of three research questions each designed to further...
Resource Type:: Masters Thesis
Full Text:: THESIS OF Steven E. Naleway for the degree of Master of Science in Materials Science presented on

Feasibility study on a soluble boron-free small modular reactor

Creator:: Mart, Justin R.
Abstract:: The elimination of soluble boron creates several advantages for Small Modular Reactor (SMR) operation. Most of these advantages are realized through significant core simplification (removal of pipes, pumping, and purification systems), the removal of the corrosive effects of soluble boron, and from improved safety effects. However, removing soluble boron creates...
Resource Type:: Masters Thesis
Full Text:: and end of cycle. Investigations of additional strategies involving an advanced control rod

External Coupling of Computational Fluid Dynamics Modeling of the Density Evolution Inside of the Helium-3 Enhanced Negative Reactivity Insertion (HENRI) System with the Monte-Carlo Neutronics code Serpent 2

Creator:: Leingang, Cole W.
Abstract:: The testing of nuclear fuel under reactivity-initiated accident (RIA) conditions is paramount for the better understanding of the fuel’s behavior during these transient accident events. The Transient Reactor Test (TREAT) facility is a nuclear reactor that will be capable of recreating the thermal-hydraulic and neutronic boundary conditions representative of RIA...
Resource Type:: Masters Thesis
Full Text:: annular control rod using a gas injection system known as the Helium-3 Enhanced Negative Reactivity

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

Dynamical System Scaling of Fuel Performance During Reactivity Insertion Accidents

Creator:: Dueñas, Alexander M.
Abstract:: Fuel qualification timelines for new fuel technology under ideal conditions can take between 20-25 years to be fully qualified from initial concept to deployment as full fuel assemblies. To reduce the timeline and costs, new separate-effects test and integral-effects test experiments, advanced instrumentation, and advanced modeling and simulation tools are...
Resource Type:: Dissertation
Full Text:: . . . . . . . . . . . . . . 76 15 Normalized rod power . . . . . . . . . . . . . . . . . . . . . . . . 80 16 SETH-C cases

Molybdenum-99 production in the Oregon State TRIGA reactor : analysis of the reactor design using a new LEU target as fuel

Creator:: Hummel, Andrew J.
Abstract:: The most widely used and versatile medical radioisotope today is technetium-99m. Roughly 30 million people depend on this radioisotope for diagnostic procedures each year, and this demand is expected to grow. Although there are numerous ways of procuring this isotope, the most common and most practical, for reasons to be...
Resource Type:: Dissertation
Full Text:: ..............................................................................67 4.1.3 Rod Worth

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

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

Creator:: Alberti, Anthony L.
Abstract:: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
Resource Type:: Masters Thesis
Full Text:: . . . . . . . . . . . . . . . . . . . . . . . . 27 2.13 Top down view of control rod configuration within full homogeneous with explicit channels

Characterization of reinforced fill soil, soil-reinforcement interaction, and internal stability of very tall MSE walls

Creator:: Walters, James J.
Abstract:: In many geotechnical design situations involving tight right-of-way constraints, Mechanically Stabilized Earth (MSE) walls are often the most cost-effective and reliable earth retention technology among available alternatives. However, few well-documented case histories with detailed material testing, instrumentation programs and construction observation of performance are available in the literature. Despite the...
Resource Type:: Masters Thesis
Full Text:: ............................................................. 216 Appendix E Pullout Box Design Calculations

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

Advancing the understanding of bulk metallic glasses as structural materials through exploration of mechanical properties

Feasibility study on a soluble boron-free small modular reactor

External Coupling of Computational Fluid Dynamics Modeling of the Density Evolution Inside of the Helium-3 Enhanced Negative Reactivity Insertion (HENRI) System with the Monte-Carlo Neutronics code Serpent 2

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

Dynamical System Scaling of Fuel Performance During Reactivity Insertion Accidents

Molybdenum-99 production in the Oregon State TRIGA reactor : analysis of the reactor design using a new LEU target as fuel

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

Characterization of reinforced fill soil, soil-reinforcement interaction, and internal stability of very tall MSE walls

Nano-Recrystallized UO₂ Microcantilever Bending After Ion Irradiation

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