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:: Michael A. Castillo for the degree of Master of Science in Nuclear Engineering presented on December 6

A CFD Analysis of a Single Channel in the Mars Hopper Engine

Creator:: Koll, Christopher J.
Abstract:: The Mars Hopper is an alternative extraterrestrial vehicle for the collection of samples from the Martian surface. This thesis studied the engine of the Mars Hopper to assess the validity of the current planned launch cycle according to current parameters. To do this, the engine was simplified to an average...
Resource Type:: Masters Thesis
Full Text:: Title: A CFD Analysis of a Single Channel in the Mars Hopper Engine Abstract approved: Andrew

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Creator:: Lenhof, Renae
Abstract:: A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...
Resource Type:: Masters Thesis
Full Text:: Probabilistic Risk Assessment of a Vented Fuel System

Fission Gas Bubble Behavior in Uranium Carbide

Creator:: Matthews, Christopher
Abstract:: The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution...
Resource Type:: Dissertation
Full Text:: enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

Creator:: Riley, Thomas H.
Abstract:: The goal of this project was to pave the way for more data-driven decision making when considering safety within Nuclear Engineering by proving the concept of new and innovative accident scenario modeling techniques for the analysis of the economics of nuclear safety margins. To do this, a simple, if extremely...
Resource Type:: Dissertation
Full Text:: modeling techniques for the analysis of the economics of nuclear safety margins. To do this, a simple

An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

Creator:: Onufer, Mark
Abstract:: The International Handbook of Evaluated Reactor Physics Benchmark Experiments contains detailed descriptions of many different reactor facilities. A large portion of these experiments have not been fully modeled due to the unavailability of computational power at the time of the experiment’s execution. With the advent of renewed interest in Sodium...
Resource Type:: Masters Thesis
Full Text:: Experiments contains detailed descriptions of many different reactor facilities. A large portion of these

Feasibility study on a soluble boron-free small modular reactor

Creator:: Mart, Justin R.
Abstract:: The elimination of soluble boron creates several advantages for Small Modular Reactor (SMR) operation. Most of these advantages are realized through significant core simplification (removal of pipes, pumping, and purification systems), the removal of the corrosive effects of soluble boron, and from improved safety effects. However, removing soluble boron creates...
Resource Type:: Masters Thesis
Full Text:: presented on June 14, 2013. Title: Feasibility Study on a Soluble Boron-Free Small Modular Reactor

Determination of a calculation bias in the MCNP model of the OSTR

Creator:: Kitto, Allyson K.
Abstract:: Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008, the reactor began operating on low enriched uranium fuel. A model of the facility exists in MCNP, a Monte Carlo code that can be used for criticality calculations. Until now, a bias in the calculation...
Resource Type:: Masters Thesis
Full Text:: . Title: Determination of a Calculation Bias in the MCNP Model of the OSTR Abstract approved

Proof of concept of the use of RAVEN and RELAP5-3D for risk informed safety margin characterization

Creator:: Riley, Thomas H.
Abstract:: This project was a proof of concept of the use of the RAVEN software, a tool developed for the Risk Informed Safety Margin Characterization (RISMC) approach, with RELAP5-3D. This novel approach combines older probabilistic and mechanistic approaches to look at how and why the complex systems of a nuclear power...
Resource Type:: Masters Thesis
Full Text:: : Andrew C. Klein This project was a proof of concept of the use of the RAVEN software, a tool

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

Creator:: Thody, Austin
Abstract:: Nuclear Thermal Rocket (NTR) designs have received renewed interest due to their superior thermal efficiencies and a rehabilitated desire for space exploration. This has resulted in improved NTR fuel designs that have unique properties that require investigation and testing in order to be more safely designed and operated. Oak Ridge...
Resource Type:: Masters Thesis
Full Text:: and a renewed desire for space exploration. This has resulted in improved NTR fuel designs that have

ScholarsArchive@OSU

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

A CFD Analysis of a Single Channel in the Mars Hopper Engine

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Fission Gas Bubble Behavior in Uranium Carbide

Proof of Concept of the use of Advanced Computational Accident Scenario Modeling for Safety Margin Economic Evaluation

An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

Feasibility study on a soluble boron-free small modular reactor

Determination of a calculation bias in the MCNP model of the OSTR

Proof of concept of the use of RAVEN and RELAP5-3D for risk informed safety margin characterization

Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

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