Index Catalog // ScholarsArchive@OSU

Classification Modeling of Nuclear Power Plant Outage Severities with Complement Naïve Bayes and Bidirectional Encoder Representations from Transformers

Creator:: Castillo, Michael A.
Abstract:: Low-level nuclear power plant outages in the United States can lead to unanticipated costs, potentially compromising the expected operation lifetime of the plant. Nuclear power plants are complex systems of interfacing components and highly regulated processes. This inherent complexity makes predicting outages from system dependencies very challenging. When outages do...
Resource Type:: Masters Thesis
Full Text:: Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

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
Full Text:: the degree of Master of Science in Nuclear Engineering presented on December 13, 2023 Title

Comparison of total dose to individuals from temperate and arid environments

Creator:: Elmore, Brockway F., II
Abstract:: This paper analyzes the decision-making process utilized in temperate environments for building nuclear facilities and whether it was going to be applicable to nuclear facilities built in arid environments. To answer this question, the total dose to individuals from arid and temperate environments were compared using RESRAD-OFFSITE and changing the...
Resource Type:: Masters Thesis
Full Text:: of Nuclear Science and Engineering Dean of the Graduate School I

An Investigation on Transient Critical Heat Flux and the Prompting Conditions

Creator:: Camargo, Angelo D.
Abstract:: The collective understanding of the critical heat flux phenomenon is crucial to the safety and operational power limits of every nuclear and petrochemical power plant in the world. To define the maximum heat transfer capability in the postulated reactivity-initiated accident in a nuclear reactor, the mechanisms that trigger the departure...
Resource Type:: Masters Thesis
Full Text:: Nuclear Science and Engineering Co-Major Professor, representing Nuclear Science and

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
Full Text:: _________________________________________________ Head of the School of Nuclear Science and Engineering

Analysis of Asymmetric Heating on a Scaled High Temperature Gas Reactor Experiment During a Pressurized Conduction Cooldown

Creator:: Moore, Thomas
Abstract:: Among the candidates for the next generation of nuclear power plant is the high temperature gas reactor (HTGR). Since the HTGR does not have the same operational history as water cooled reactors do in the United States, investigation into the response of different accident phenomena is still an active area...
Resource Type:: Dissertation
Full Text:: APPROVED: Major Professor, representing Nuclear Engineering Head of the School of Nuclear Science and

Small Scale Modeling of a Broad Area Detector Network Array

Creator:: Johnson, Patrick M.
Abstract:: Nuclear material monitoring systems have long been established at ports of entry. However, there are no standard systems for monitoring points of interest within the country. Therefore, the use of a network of radiation sensors deployed throughout an area of interest is being investigated within this thesis. Before full scale...
Resource Type:: Masters Thesis
Full Text:: Professor, representing Radiation Health Physics Head of the Department of Nuclear Science and

Nanoscale Instrumented Indentation Testing with the Current Capabilities of MOOSE and Marmot

Creator:: VandenBroeder, Gavin T.
Abstract:: Nanoscale Instrumented Indentation Testing (IIT) is a material characterization technique that is used to determine mechanical properties. The size effects present at this scale make it difficult to expand findings to a bulk scale. Modeling can be used to bridge this gap and better understand nanoscale IIT and the size...
Resource Type:: Masters Thesis
Full Text:: Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I

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
Full Text:: , representing Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

Risk-Informed Performance-Based Methods for Cyber-Attack on Nuclear Power Facilities

Creator:: Gisondi, Andrew
Abstract:: A new approach is described that offers a risk-informed performance-based (RIPB) framework for quantifying the risk associated with a cyber-attack on a nuclear power generating facility. The first part of the method involves 1) the creation of a simplified 10 CFR 73.54 compliant cyber infrastructure, 2) modeling of design basis...
Resource Type:: Masters Thesis
Full Text:: the School of Nuclear Science and Engineering Dean of the Graduate School I understand that my

ScholarsArchive@OSU

Classification Modeling of Nuclear Power Plant Outage Severities with Complement Naïve Bayes and Bidirectional Encoder Representations from Transformers

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

Comparison of total dose to individuals from temperate and arid environments

An Investigation on Transient Critical Heat Flux and the Prompting Conditions

Out-of-pile blowdown critical heat flux experiment

Analysis of Asymmetric Heating on a Scaled High Temperature Gas Reactor Experiment During a Pressurized Conduction Cooldown

Small Scale Modeling of a Broad Area Detector Network Array

Nanoscale Instrumented Indentation Testing with the Current Capabilities of MOOSE and Marmot

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

Risk-Informed Performance-Based Methods for Cyber-Attack on Nuclear Power Facilities

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