Index Catalog // ScholarsArchive@OSU

Experimental Study of the Impact of Physical and Chemical Properties on Smoldering Combustion in Natural Fuels

Creator:: Smucker, Benjamin
Abstract:: Smoldering combustion in wildland fires is difficult to extinguish, can transition to flaming combustion, and produces a significant amount of pollutants. It is necessary to understand parameters controlling smoldering in order to help predict the smoldering behavior and potentially mitigate these hazards. The wide variety of natural fuels that occur...
Resource Type:: Dissertation

Validation Analysis for the OSU HTTF PG-28 Test Using RELAP5-3D and STAR-CCM+

Creator:: Halsted, Joshua K.
Abstract:: High temperature gas reactors (HTGR’s) have been researched and operated commercially since the inception of the nuclear industry. Newer designs, such as the General Atomics (GA) Modular HTGR, aim to lower capital costs by shifting towards smaller, more modular designs, although further cost reductions with respect to operations and maintenance...
Resource Type:: Masters Thesis

Diffusion Accelerated Implicit Monte Carlo via Nonlinear Elimination for Thermal Radiative Transfer

Creator:: Lam, Adam Q.
Abstract:: In this dissertation, we derive and implement a new transport-diffusion hybrid algorithm for solving thermal radiative transfer (TRT) problems. Using the method of nonlinear elimination (NLEM), the TRT system of equations can be written in terms of a transport equation with the absence of scattering and a diffusion equation. The...
Resource Type:: Dissertation

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

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

Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

Creator:: Yoshiura, Ramon K.
Abstract:: The development of nuclear fuel and materials requires is a continuous effort to investigate the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or other conceivable damage mechanics acquired during normal operation or accident scenarios throughout its lifetime. As in-core fuel property measurement techniques advance to support in...
Resource Type:: Dissertation

On the mechanism transition of power transient critical heat flux

Creator:: Yan, Yikuan
Abstract:: The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
Resource Type:: Dissertation

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

Design of a Pebble Bed Separate Effects Test for Molten Salt Reactors

Creator:: Uselman, Jacob S.
Abstract:: The licensing of novel nuclear reactor power plant designs requires extensive research and testing. A significant portion of this work is dedicated to the design and operation of scaled-down testing facilities that emulate various plant conditions. The data gathered from these test facilities is used to compare to predictive models....
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

ScholarsArchive@OSU

Experimental Study of the Impact of Physical and Chemical Properties on Smoldering Combustion in Natural Fuels

Validation Analysis for the OSU HTTF PG-28 Test Using RELAP5-3D and STAR-CCM+

Diffusion Accelerated Implicit Monte Carlo via Nonlinear Elimination for Thermal Radiative Transfer

Development of a Rapid Power Transient Critical Heat Flux Model

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

Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

On the mechanism transition of power transient critical heat flux

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Design of a Pebble Bed Separate Effects Test for Molten Salt Reactors

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

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