Index Catalog // ScholarsArchive@OSU

A Numerical Investigation into Capillary-Wrapped Liquid Sodium Pin-Bundles for Instrumentation Development

Creator:: Vietz, Stefan
Abstract:: Liquid sodium is a challenging fluid to perform verification and validation for. Its chemical reactivity, large thermal conductivity, and opacity make both modeling and experimental data gathering difficult. Converting the wire wraps of liquid sodium reactor fuel pin geometry into capillaries, and inserting fiber optic temperature sensors, promises to capture...
Resource Type:: Masters Thesis

Out-of-pile blowdown critical heat flux experiment

Creator:: Moussaoui, Musa A.
Abstract:: In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is not yet determined whether the use of steady-state CHF methods can accurately predict transient CHF under the conditions of a blowdown due...
Resource Type:: Dissertation

Validation of a Transient Coupled CFD-Reactor Physics Model: An Experimental Methodology to Quantify the Accuracy of CONSTELATION for the HENRI System

Creator:: Warren, Austin M.
Abstract:: The HENRI system was developed to narrow the pulse width of TREAT from 89 ms to below 60 ms with the goal of improving the test reactor's ability to simulate RIAs in LWRs by rapidly injecting helium-3, a strong neutron poison, into the core. A coupled model using the CFD...
Resource Type:: Masters Thesis

CFD Verification, Validation, and Sensitivity Study of Internally Heated Concentric Tube Thermosyphon O-SERTTA

Creator:: Miller, Jaden
Abstract:: Irradiation experiments are a critical aspect of the nuclear fuels and materials qualification process. Determining the flow conditions of these experiments is necessary for understanding response of nuclear components during transient and normal operation. Quality flow data is lacking for cartridge-type irradiation experiments with annular flow natural circulation designs. Data...
Resource Type:: Masters Thesis

Thermal Stability of Advanced Metallic Nuclear Fuel Microstructures

Creator:: Wright, Alexander A.
Abstract:: Metallic nuclear fuels have long been studied for use in advanced nuclear reactors, with efforts invested in improving the viability of metallic nuclear fuel elements and overall safety of advanced reactor design concepts. During reactor operations, fuel forms undergo restructuring due to a variety of physical phenomena. Expansion of the...
Resource Type:: Masters Thesis

Quantifying System Distortions between the VTR and IVTR facilities through H2TS Scaling Methodology and RELAP5-3D Simulations

Creator:: Johnson, Juwan A.
Abstract:: Sodium Cooled Fast Reactors (SFR) are complex and expensive due to high operating temperatures and neutron flux which pose technical challenges for these reactors. To overcome these challenges with SFRs, research and development of small scale and large-scale facilities are needed to bridge the gap in understanding. Scaling analyses develop...
Resource Type:: Masters Thesis

Quantifying System Similarity Between EBR-II and the VTR Integral Test Facility Through Hierarchical Two-Tiered Scaling and RELAP5 Simulations

Creator:: Leitherer, Brett C.
Abstract:: Advanced reactor designs offer many advantages over typical Light Water Reactors (LWRs) including fast neutron capability, passive safety features, and improved performance. While the future for these reactors seems promising, operating and test experience is necessary to further validate such claims. The development of full-scale facilities has proved to be...
Resource Type:: Masters Thesis

Fuel Dispersal Under LOCA Conditions

Creator:: Latimer, Griffen D.
Abstract:: Most operating power reactors use oxide fuel in the form of uranium oxide (UO2) which is robust against high temperatures but suffers from poor mechanical performance at high levels of burnup. Currently, the maximum average burnup in light water reactors in the US is 62.5 GWd/t, which is partially imposed...
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

Design, Fabrication, and Evaluation of a Novel High-Performance Resistance Heater Rod for Nuclear Thermal Hydraulic Experimentation

Creator:: Sharaf, Salem A.
Abstract:: The Accident Tolerant Fuels campaign demonstrated a need for nuclear fuel pin simulators to further research fuel and cladding combinations that can withstand off normal conditions in light water reactors. The use of a heater rod as a fuel pin simulator greatly reduces the risk involved during testing as no...
Resource Type:: Masters Thesis

ScholarsArchive@OSU

A Numerical Investigation into Capillary-Wrapped Liquid Sodium Pin-Bundles for Instrumentation Development

Out-of-pile blowdown critical heat flux experiment

Validation of a Transient Coupled CFD-Reactor Physics Model: An Experimental Methodology to Quantify the Accuracy of CONSTELATION for the HENRI System

CFD Verification, Validation, and Sensitivity Study of Internally Heated Concentric Tube Thermosyphon O-SERTTA

Thermal Stability of Advanced Metallic Nuclear Fuel Microstructures

Quantifying System Distortions between the VTR and IVTR facilities through H2TS Scaling Methodology and RELAP5-3D Simulations

Quantifying System Similarity Between EBR-II and the VTR Integral Test Facility Through Hierarchical Two-Tiered Scaling and RELAP5 Simulations

Fuel Dispersal Under LOCA Conditions

On the mechanism transition of power transient critical heat flux

Design, Fabrication, and Evaluation of a Novel High-Performance Resistance Heater Rod for Nuclear Thermal Hydraulic Experimentation

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