Index Catalog // ScholarsArchive@OSU

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 study of the depressurized conduction cooldown event in the high temperature test facility using RELAP5-3D/ATHENA

Creator:: Aldridge, Robert J.
Abstract:: In 2008, the Department of Energy (DOE) and Nuclear Regulatory Commission (NCR) decided that the Next Generation Nuclear Plant (NGNP) would be the Very High Temperature Reactor (VHTR). In support of the licensing and validation effort of the VHTR, Oregon State University was tasked with designing, building, and operating a...
Resource Type:: Masters Thesis
Full Text:: Robert J. Aldridge for the degree of Master of Science in Nuclear Engineering presented on May 29, 2013

Feasibility of GOTHIC for a Pressurized Conduction Cooldown Event in the High Temperature Test Facility

Creator:: Brawley, Luke P.
Abstract:: The purpose of this work was to explore the feasibility of using the GOTHIC thermal hydraulics software package to model a pressurized conduction cooldown event in the High Temperature Test Facility. To achieve that aim, a model of the facility was constructed in the GOTHIC software and a selection of...
Resource Type:: Masters Thesis
Full Text:: : ________________________________________________________________________ Brian G. Woods The purpose of this work was to explore the feasibility of using the GOTHIC

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

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

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

System model of a natural circulation integral test facility

Creator:: Galvin, Mark Robert, 1967-
Abstract:: The Department of Nuclear Engineering and Radiation Health Physics (NE/RHP) at Oregon State University (OSU) has been developing an innovative modular reactor plant concept since being initiated with a Department of Energy (DoE) grant in 1999. This concept, the Multi-Application Small Light Water Reactor (MASLWR), is an integral pressurized water...
Resource Type:: Dissertation
Full Text:: Facility Abstract approved: Brian G. Woods The Department of Nuclear Engineering and Radiation Health

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

Creator:: Blake, Grant C.
Abstract:: The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system capable of removing decay heat directly from the reactor core. Its modularity makes it scalable for use in reactors with various power levels. Work has previously been completed to support inclusion of the DRACS in liquid metal reactors...
Resource Type:: Masters Thesis
Full Text:: Depressurized Loss of Forced Convection Event Abstract approved: Brian G. Woods The Direct Reactor

RELAP5-3D modeling of ADS blowdown of MASLWR facility

Creator:: Bowser, Christopher Jordan
Abstract:: Oregon State University has hosted an International Atomic Energy Agency (IAEA) International Collaborative Standard Problem (ICSP) through testing conducted on the Multi-Application Small Light Water (MASLWR) facility. The MASLWR facility features a full-time natural circulation loop in the primary vessel and a unique pressure suppression device for accident scenarios. Automatic...
Resource Type:: Masters Thesis
Full Text:: Modeling of ADS Blowdown of MASLWR Facility Abstract approved: Brian G. Woods Oregon State University

ScholarsArchive@OSU

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

Scaling study of the depressurized conduction cooldown event in the high temperature test facility using RELAP5-3D/ATHENA

Feasibility of GOTHIC for a Pressurized Conduction Cooldown Event in the High Temperature Test Facility

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

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

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

System model of a natural circulation integral test facility

Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

RELAP5-3D modeling of ADS blowdown of MASLWR facility

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