Index Catalog // ScholarsArchive@OSU

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program

Creator:: Robinson, Adam B.
Abstract:: This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease the use of high enriched uranium in research and test reactors around the world, new fuels with high uranium densities must be developed such...
Resource Type:: Masters Thesis

An experimental study of laminarization induced by acceleration and curvature

Creator:: Jackson, R. Brian
Abstract:: The Generation IV Very High Temperature Reactor (VHTR) design is being actively studied in various countries for application due to its inherent passive safe design, higher thermal efficiencies, and proposed capability of providing high temperature process heat. The pebble bed core is one of two core designs used in gas...
Resource Type:: Dissertation
Full Text:: ABSTRACT OF THE DISSERTATION OF R. Brian Jackson for the degree of Doctor of Philosophy in Nuclear

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

Creator:: Weiss, Aaron W.
Abstract:: A large, multi-year experimental program has been conducted to develop a strain gaging program for application to the flow testing of prototypic, plate-type fuel for high performance research reactors. This test program has resulted in the selection of appropriate strain gage construction, adhesives, and protective coatings to allow the acquisition...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: Brian G. Woods A large, multi-year experimental program has been conducted to develop

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:: : ______________________________________________________ Brian Woods Among the candidates for the next generation of nuclear power plant is the high

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Creator:: Mai, Anh T.
Abstract:: The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
Resource Type:: Masters Thesis
Full Text:: Using VIPRE-01 and FRAPCON-3 Abstract approved: Brian G. Woods The Multi

Effect of Initial System Temperature on Initiation of Natural Circulation during a Depressurized Conduction Cooldown Event in the High Temperature Test Facility

Creator:: Brumback, Kyle E.
Abstract:: High Temperature Gas Reactors (HTGR) are a type of power plants that can provide industrial process heat and high efficiency, carbon-free electricity. The High Temperature Test Facility (HTTF) has been designed to provide data that can be used for the validation of system codes and verification of passive safety features...
Resource Type:: Masters Thesis
Full Text:: . Abstract approved: ______________________________________________________ Brian G. Woods High

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Creator:: Castañeda, Juan A.
Abstract:: In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...
Resource Type:: Masters Thesis
Full Text:: EVENT USING RELAP5- 3D Abstract approved: Brian G. Woods In early 2000, the

CFD analysis of pressure differentials in a plate-type fuel assembly

Creator:: Roth, Gable D.
Abstract:: The Hydro-Mechanical Fuel Test Facility (HMFTF) is being built at Oregon State University to evaluate fluid flow through plate-type fuel assemblies. The first plate assembly that will be examined in the facility is the Generic Test Plate Assembly (GTPA). The GTPA consists of an array of six parallel flat plates,...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: _____________________________________________________________________ Brian G. Woods

The Development of a Hybrid Particle-in-Cell Simulation Code in C++ for the Modeling of the SPT-70 Hall Thruster

Creator:: Myers, Conner J.
Abstract:: In order to support the growing satellite propulsion industry, a hybrid Particle-In-Cell (PIC) simulation with fluid treatment of electrons and neutral particles was developed to model the SPT-70 Hall thruster. The 2D, C++ code assumes azimuthal symmetry and a uniform magnetic field in the radial direction with the simulation domain...
Resource Type:: Masters Thesis
Full Text:: : ______________________________________________________ Brian G. Woods In order to support the growing satellite propulsion industry, a hybrid

Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility

Creator:: Nelson, Benjamin L.
Abstract:: The Very High Temperature Reactor (VHTR) has two possible core configurations, a hexagonal prismatic and a pebble bed. It is essential that an experimental facility be built for the validation of computer codes for the safe operation of the VHTR. The scaling of the prismatic core configuration has been analyzed...
Resource Type:: Masters Thesis
Full Text:: : _____________________________________________________________________ Brian G. Woods The Very High Temperature Reactor (VHTR) has two possible core

ScholarsArchive@OSU

High uranium density dispersion fuel for the reduced enrichment of research and test reactors program

An experimental study of laminarization induced by acceleration and curvature

Development of a Strain Gage Program for the Measurement of Strain on Prototypic, Plate-type, High Performance Research Reactor Fuels under Flow Testing

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

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Effect of Initial System Temperature on Initiation of Natural Circulation during a Depressurized Conduction Cooldown Event in the High Temperature Test Facility

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

CFD analysis of pressure differentials in a plate-type fuel assembly

The Development of a Hybrid Particle-in-Cell Simulation Code in C++ for the Modeling of the SPT-70 Hall Thruster

Scaling analysis for the pebble bed of the very high temperature gas-cooled reactor thermal hydraulic test facility

Limit your search

Academic Affiliation

Advisor

Commencement Year

Committee Member

Creator

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