Index Catalog // ScholarsArchive@OSU

Experimental Investigation of the Transition to Natural Convection in HTGR Applications using the Oregon State SFSETF

Creator:: Fishler, Joshua D.
Abstract:: High Temperature Gas Reactors (HTGRs) are positioned to disrupt local and global markets via their unique ability to produce carbon-free process heat, high efficiency power generation, and passively safe operational features. However, significant impediments still exist to delay deployment of this particular technology, including a lack of experimental data, verified...
Resource Type:: Dissertation
Full Text:: this particular technology, including a lack of experimental data, verified code application, and

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:: advanced control rod algorithm is thus recognized as a viable strategy for boron-free operation for SMRs

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Creator:: VanWinkle, James A.
Abstract:: A study of the oxidation of zircaloy in reactor environments has been undertaken with the goal of characterizing of the Thermal Gradient Test Facility (TGTF) at Teledyne Wah Chang, Albany. A set of oxidation models is presented from the literature, as well as an extensive database of published oxidation test...
Resource Type:: Masters Thesis
Full Text:: examination of the corrosion of a simulated fuel rod under heated conditions. Finally, a manual for the

Preliminary framework for the run-ahead predictive simulation software (RAPSS)

Creator:: Makinson, Kevin A.
Abstract:: The Run-Ahead Predictive Simulation Software (RAPSS) is an architecture designed for faster-than-real-time decision support for operators of complex networks. To enable further development of the RAPSS methodology, the necessary proof of principle is illustrated in two applications: decision support for shift technical advisors in nuclear power plant control rooms (RAPSS-STA),...
Resource Type:: Dissertation
Full Text:: AN ABSTRACT OF THE DISSERTATION OF Kevin A

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:: assemblies as a function of moderator density, cell geometry, control-rod position, fuel temperature, etc

The Control and Safety Analysis of a Small Fission Surface Power Reactor

Creator:: Nelson, Noel B.
Abstract:: The NKUA1 is a Small Fission Surface Power (SFSP) space reactor intended for use in upcoming missions to Mars and the moon between the years 2020-2030. The concept of the reactor was created by Dr. Lee Mason and his research team in a joint effort between the Department of Energy...
Resource Type:: Honors College Thesis
Full Text:: control design suggested by Lee Mason et al. consisted of two components: a large control rod in the

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

Creator:: Merritt, Patrick A.
Resource Type:: Masters Thesis
Full Text:: by the ejection of a control rod). The excess positive reactivity is automatically overcome by the

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

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:: heat from the fuel rod. Furthermore, the reduction in cladding strain allows for a reduction in

System modeling and reactor design study of an advanced incore thermionic space reactor

Creator:: Lee, Hsing Hui
Abstract:: Incore thermionic space reactor design concepts which operate at a nominal power output range of 20 to 50 kWe are described. Details of the neutronic, thermionic, thermal hydraulics and shielding performance are presented. Due to the strong absorption of thermal neutrons by natural tungsten, and the large amount of that...
Resource Type:: Masters Thesis
Full Text:: number of driver rod positions required. Lower power level for a given core diameter. One of the main

ScholarsArchive@OSU

Experimental Investigation of the Transition to Natural Convection in HTGR Applications using the Oregon State SFSETF

Feasibility study on a soluble boron-free small modular reactor

Oxidation of Zircaloy-4 in pressurized water reactor conditions

Preliminary framework for the run-ahead predictive simulation software (RAPSS)

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

The Control and Safety Analysis of a Small Fission Surface Power Reactor

MCNP benchmarking and analysis of Oregon State University TRIGA Reactor

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

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

System modeling and reactor design study of an advanced incore thermionic space reactor

Limit your search

Academic Affiliation

Advisor

Commencement Year

Committee Member

Creator

Contributor

Date

Decade

Degree Field

Degree Level

Degree Name

Language

License

Non-Academic Affiliation

Peer Reviewed

Resource Type

Rights Statement

Subject

Search Constraints

Search Results

Limit your search