Index Catalog // ScholarsArchive@OSU

A thermal hydraulics analysis of a molybdenum production element for implementation in TRIGA reactors

Creator:: Byfield, Patrick
Abstract:: The metastable isotope of technetium-99 (Tc-99m) is an important diagnostic tool used in the field of nuclear medicine due to the isotope's 6.0 hour half-life, 140.5 keV γ-decay mechanism, and multiple oxidation states [1,2]. Approximately 70% of the world’s nuclear medicine procedures involve the use of Tc-99m [3]. The conventional...
Resource Type:: Masters Thesis
Full Text:: , wherein the fluid is heated by fuel rods near the bottom of the reactor pool and cooling is provided by

Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF

Creator:: Latimer, Griffen D.
Abstract:: Current research on the topic of advanced reactor fuel types include the use of ultrahigh density Uranium-Molybdenum fuels, towards their use in high-performance research reactors. These reactors operate with high power densities, and the increased cooling requirements therefore place high relevance on the fluid-structure interaction with these fuel elements; therefore...
Resource Type:: Masters Thesis
Full Text:: conveying fluid. Numerous studies have investigated the dynamic response of shells under these conditions

Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

Creator:: Cox, Jordan
Abstract:: The United States (US) Department of Energy (DOE) has identified the pebble-bed reactor as a high priority for US research with the end goal of licensing a pebble-bed reactor (PBR) for operation in the United States. Before this can be accomplished significant research must be done regarding the safety of...
Resource Type:: Masters Thesis
Full Text:: likelihood of a nuclear accident using fuel design and material properties. To this end this company began

Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

Creator:: Lee, Dongyoung
Abstract:: There is renewed interest in the reliability and safety of nuclear power plants following the Fukushima Daiichi nuclear accident followed by 8.9 magnitude earthquake and Tsunami with the height of 15 m on March 11, 2011. Small Modular Reactors (SMRs) have been developed to improve safety systems by utilizing passive...
Resource Type:: Dissertation
Full Text:: integral PWR, which consists of nuclear fuel, control rod drives, SG, pressurizer and reactor coolant

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:: production of synthetic fuels. To satisfy future demand for transportation fuel, nuclear process heat may

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
Full Text:: An Approach to Modeling Fuel Plate Deformations in Fluid

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:: to a nuclear core's fuel assemblies. The lower core plate and shroud around the core keep the

Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

Creator:: Utberg, John E., Jr
Abstract:: The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...
Resource Type:: Masters Thesis
Full Text:: codes. Although the HTTF is a scaled-down model of a nuclear reactor, there is no nuclear fuel in the

A study of buoyant backflow in vertical injection lines

Creator:: King, John Barry
Abstract:: In the event of a small break loss of coolant accident (SBLOCA) in a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to compensate for the coolant loss. When this flow rate is less than a critical value, however, the hot fluid in the cold...
Resource Type:: Dissertation
Full Text:: a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

Creator:: Jensen, Philip
Abstract:: The Oregon State University (OSU), Hydro Mechanical Fuel test Facility (HMFTF) is designed to hydro-mechanically test prototypical plate type fuel. OSU's fuel test program is a part of the Global Threat Reduction Initiative (GTRI), formerly known as the Reduced Enrichment for Research and Test Reactor program. One of the GTRI's...
Resource Type:: Masters Thesis
Full Text:: enriched uranium (HEU) to a low enriched uranium (LEU) fuel in an effort to reduce nuclear proliferation

ScholarsArchive@OSU

A thermal hydraulics analysis of a molybdenum production element for implementation in TRIGA reactors

Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF

Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

Flow Dynamics and Condensation of Film Flows in Small Modular Reactors

Modification of Lower Plenum Structure for Mixing Promotion during Normal Operation of the High Temperature Gas Cooled Reactor

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

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

Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

A study of buoyant backflow in vertical injection lines

Application of sandwich structure analysis in predicting critical flow velocity for a laminated flat plate

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