Index Catalog // ScholarsArchive@OSU

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:: their time and friendship. Jarvis Caffrey, Brian Gullekson, Kevin Makinson, Robert Schikler, and

A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

Creator:: Jackson, R. Brian
Abstract:: Downward flow opposing mixed convection conditions have been studied using the FLUENT CFD code. This work was comprised of two primary objectives. The first was to study core channel flow reversal susceptibility in the Gas Reactor Test Section (GRTS) at low flow conditions. The second objective was the development of...
Resource Type:: Masters Thesis
Full Text:: fly_leaf AN ABSTRACT OF THESIS OF R. Brian

On the Role of Particle Size Distribution in Selective Laser Melting of 316L Stainless Steel

Creator:: Coe, Hannah G.
Abstract:: Selective laser melting (SLM) is an additive manufacturing (AM) process that uses a laser beam to melt metal powder as it is spread onto the build surface using a roller or scraper, followed by rapid solidification to manufacture a 3D component, one layer at a time. In SLM process, density...
Resource Type:: Masters Thesis
Full Text:: ). SLM was performed in nitrogen atmosphere at volumetric energy densities (VED) ranging from 35.7 J

Heat Transfer Coefficient Correlation Development of Dowtherm A in the Near Wall Region of a Pebble Bed Reactor

Creator:: Dionne, Connor J.
Abstract:: Computational fluid dynamics conjugate heat transfer simulations were performed on a packed bed test facility using Dowtherm-A as the working fluid. Multiple test cases were simulated for a Reynolds number range of 188 – 1524 and a set heater power of 60 kW. Temperature profiles were extracted, and the near-wall...
Resource Type:: Masters Thesis
Full Text:: support, tips, and workarounds to my problems. I would also like to thank Dr. Brian Jackson from Kairos

Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

Creator:: Danielson, Jordan J.
Abstract:: All nuclear reactors rely heavily on the use of level sensing instrumentation to detect the behaviour of liquid in vessels. The majority of level sensing instruments are differential pressure sensing meters, which are invasive and could be the failure source in the pressure boundary of the primary coolant system. In...
Resource Type:: Masters Thesis
Full Text:: AN ABSTRACT OF THE THESIS OF Jordan J. Danielson for

Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

Creator:: Wuth, Bradyn J.
Abstract:: Some of the next generation of small modular reactors have been designed with helically coiled steam generators integrated into the reactor vessel to enhance natural circulation. According to the developers of TASS/SMR, a one-dimensional thermal hydraulic code written to model the Korean Atomic Energy Research Institute's SMART reactor, the Žukauskas...
Resource Type:: Masters Thesis
Full Text:: from the OSU MASLWR Test Facility Steam Generator AN ABSTRACT OF THE THESIS OF Bradyn J. \uth for

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Creator:: Reynolds, Aaron J.
Abstract:: Circulating fuel reactor (CFR) kinetics are characterized by delayed neutron precursor (DNP) drift in addition to the neutronic and thermal hydraulic phenomena typical of other reactor types. This environment can be computationally challenging to model, given that the multiphysics phenomena generally have non-linear interdependencies requiring the use of iterative solution...
Resource Type:: Dissertation
Full Text:: . . . . . . . . . . . . . . . . . . . . . . . . 42 3.3 Subcell discretization on a cell (i, j) . . . . . . . . . . . . . . . . . . 44 3.4 Beginning

Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

Creator:: Nes, Razvan
Abstract:: An important improvement in the area of reactor core neutronic modeling is the development and use of the methods based on "quasi-diffusion" (QD) low-order equations. This family of methods takes into account the transport exactly using "functionals" computed by solving transport equations, and is amenable to solution with a variety...
Resource Type:: Dissertation
Full Text:: 4 ˆ ˆˆ ˆ( , ) ( )i g gid r J r

Development of a Rapid Power Transient Critical Heat Flux Model

Creator:: Brown, Emory G.
Abstract:: The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...
Resource Type:: Dissertation
Full Text:: abilities as a young researcher. I would also like to thank my committee members, Dr. Brian Woods, Dr

An Approach to Modeling Fuel Plate Deformations in Fluid-Structure Interactions

Creator:: Howard, Trevor
Abstract:: As computational power increases, so does the desire to use fluid-structure interaction (FSI) software to design complex systems and components such as fuel plates. Presently, an effort is underway to support the design and qualification of a new nuclear fuel material which is intended for applications in select, plate-type, research...
Resource Type:: Masters Thesis

ScholarsArchive@OSU

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

A study of opposing mixed convection in the GRTS and in downward pipe flows using the FLUENT CFD code

On the Role of Particle Size Distribution in Selective Laser Melting of 316L Stainless Steel

Heat Transfer Coefficient Correlation Development of Dowtherm A in the Near Wall Region of a Pebble Bed Reactor

Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

Development of a Rapid Power Transient Critical Heat Flux Model

An Approach to Modeling Fuel Plate Deformations in Fluid-Structure Interactions

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