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:: : ______________________________________________________ Andrew C. Klein Low-level nuclear power plant outages in the United States can lead to

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:: approved: ______________________________________________________ Andrew C. Klein Nuclear

Experimental simulations of a rotating bubble membrane radiator for space nuclear power systems

Creator:: Al-Baroudi, Homan Mohammed-Zahid
Abstract:: A rotating, flat plate condensation experiment has been developed to investigate the heat of the Rotating Bubble Membrane Radiator (RBMR). The RBMR is a proposed heat rejection system for space applications which uses working fluid condensation on the inside surface of a rotating sphere to reject heat to space. The...
Resource Type:: Dissertation
Full Text:: Approved: Andrew C.' Klein A rotating, flat plate condensation experiment has been developed to

Top-down scaling analysis of the integral reactor vessel test facility

Creator:: Graves, Joshua D.
Abstract:: Oregon State University has conducted research in collaboration with TerraPower, LLC, to perform a top-down scaling analysis of an integrated test facility. The goal of this facility is to simulate transient and quasi-steady phenomena at a reduced scale, including steady-state operation, pump coastdown, natural circulation, reactor head heat transfer, and...
Resource Type:: Masters Thesis
Full Text:: Integral Reactor Vessel Test Facility Abstract approved: Andrew C. Klein Oregon State University has

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:: : Andrew C. Klein Oregon State University is home to a TRIGA® Mark II reactor. In October of 2008

Preliminary design and analysis of a rotating bubble membrane radiator for space-based nuclear power systems

Creator:: Webb, Brent Jonathan
Abstract:: The development of a novel high temperature space radiator is described. A Rotating Bubble Membrane Radiator (RBMR) combines the best features of heat pipes and droplet radiators while avoiding their negative attributes. The RBMR offers light weight, self deployment, ease of startup and its performance is less affected by acceleration....
Resource Type:: Masters Thesis
Full Text:: interplanetary space with an average velocity of 20 km/s and a density of 0.5 g/cm3. While the masses of

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

Creator:: Al-Kheliewi, Abdullah S.
Abstract:: A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...
Resource Type:: Dissertation
Full Text:: Doctor of Philosophy Completed September 20, 1993 Commencement June, 1994 APPROVED: Andrew

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Creator:: Abdul-hamid, Shahab A.
Abstract:: Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...
Resource Type:: Masters Thesis
Full Text:: Nuclear Power System. Abstract Approved: Andrew C. Klein Lattice bum-up calculations in thermal reactors

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Creator:: Merritt, Patrick A.
Resource Type:: Masters Thesis
Full Text:: Oregon State University TRIGA Reactor Abstract approved: Andrew C. Klein The impetus for this

ScholarsArchive@OSU

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

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

Experimental simulations of a rotating bubble membrane radiator for space nuclear power systems

Top-down scaling analysis of the integral reactor vessel test facility

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

Preliminary design and analysis of a rotating bubble membrane radiator for space-based nuclear power systems

Modeling transient thermalhydraulic behavior of a thermionic fuel element for nuclear space reactors

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

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