Index Catalog // ScholarsArchive@OSU

The Modeling of Core-Wide Behavior of Pebble Bed Reactors Using Static and Dynamic Graphite Pebble Properties to Predict Core Performance and Safety Behaviors

Creator:: Cox, Jordan T.
Abstract:: The United States Department of Energy 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 the pebble-bed...
Resource Type:: Dissertation
Full Text:: : _____________________________________________________________________ Brian G. Woods The United States Department of Energy has identified the pebble-bed reactor as

Predicting mechanical instability of a cylindrical plate under axial flow conditions

Creator:: Marcum, Wade R.
Abstract:: Five U.S. high performance research reactors (HPRRs) are currently part of an international nonproliferation program with the objective of ultimately converting their highly enriched uranium (HEU) fuel to a new high density, low enriched uranium (LEU) fuel while still maintaining their reactor kinetic and thermal hydraulic performance. A uranium-molybdenum (U-Mo)...
Resource Type:: Dissertation
Full Text:: Conditions Abstract approved: ________________________________________________ Brian G. Woods

Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D

Creator:: Marcum, Wade R.
Abstract:: Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: _____________________________________________________________________ Brian G

Modeling the Fusion Reaction in an Inertial Electrostatic Confinement Reactor with the Particle-in-Cell Method

Creator:: van de Lindt, Jacob
Abstract:: Nuclear fusion has the potential to meet the energy needs of our civilization for centuries to come and does not produce harmful greenhouse gasses or produce long-lasting radioactive waste. A fusion reaction can be readily demonstrated in a confinement scheme known as inertial electrostatic confinement (IEC) fusion. In this work,...
Resource Type:: Honors College Thesis
Full Text:: Brian Woods, Mentor, representing the Department of Nuclear Engineering

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:: Brian Woods Sodium cooled nuclear reactors are being considered for the next generation of nuclear

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:: : _____________________________________________________ Brian G. Woods Piotr Furmański Since High Temperature Gas-cooled

Development of a binary mixture gas composition instrument for use in a confined high temperature environment

Creator:: Cadell, Seth R.
Abstract:: With recent advancements in material science, industrial operations are being conducted at higher and higher temperatures. This is apparent in the nuclear industry where a division of the field is working to develop the High Temperature Gas Reactor and the Very High Temperature Gas Reactor concurrently. Both of these facilities...
Resource Type:: Dissertation
Full Text:: : _____________________________________________________________________ Brian G. Woods With recent advancements in material science, industrial operations are being

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:: : _____________________________________________________________________ Brian G. Woods The United States (US) Department of Energy (DOE) has identified the pebble

Pressure effects on density-difference driven stratified flow : CFD model of DCC event in the HTGR

Creator:: Magnusson, Jill E.
Abstract:: In a Modular High Temperature Gas Reactor (MHTGR), the Depressurized Conduction Cooldown (DCC) event can be separated into three distinct stages: 1) depressurization, 2) air ingress and, 3) natural circulation. During normal operations, the HTGR utilizes forced convection to move the helium coolant through the reactor core. Thus, during normal...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: _____________________________________________________________________ Brian G. Woods

Effect of Initial Conditions and Depressurization on Lock Exchange Flow After a Depressurized Conduction Cool-Down Event in the High Temperature Test Facility

Creator:: Glass, Molly
Abstract:: The High Temperature Test Facility (HTTF) is an electrically heated, scaled model of a Modular High Temperature Gas Reactor (MHTGR). Five experiments were conducted to study Depressurized Conduction Cool-Down phenomena stemming from a Double-Ended Guillotine Break (DEGB). After a DEGB, the reactor pressure vessel would depressurize until the pressures are...
Resource Type:: Masters Thesis
Full Text:: : ______________________________________________________ Brian G. Woods The High Temperature Test Facility (HTTF) is an electrically heated

ScholarsArchive@OSU

The Modeling of Core-Wide Behavior of Pebble Bed Reactors Using Static and Dynamic Graphite Pebble Properties to Predict Core Performance and Safety Behaviors

Predicting mechanical instability of a cylindrical plate under axial flow conditions

Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D

Modeling the Fusion Reaction in an Inertial Electrostatic Confinement Reactor with the Particle-in-Cell Method

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

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

Development of a binary mixture gas composition instrument for use in a confined high temperature environment

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

Pressure effects on density-difference driven stratified flow : CFD model of DCC event in the HTGR

Effect of Initial Conditions and Depressurization on Lock Exchange Flow After a Depressurized Conduction Cool-Down Event in the High Temperature Test Facility

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