Index Catalog // ScholarsArchive@OSU

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

Development of a Novel MEMS Thermal Sensor Array for Pebble Bed HTGRs

Creator:: Hertel, Matthew A.
Abstract:: A novel high temperature thermal instrument is proposed, which utilizes a dual-sensing platinum resistor encased in a mono-crystalline alpha-alumina (sapphire) substrate. The instrument is comprised of four platinum trace elements, oriented with 90° rotational symmetry atop a 1120 oriented crystal lattice substrate. All four of these sensors measure temperature directly...
Resource Type:: Dissertation

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

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

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

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

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

Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor

Creator:: Gutowska, Izabela
Abstract:: To understand how a Depressurized Loss of Forced Convection (D-LOFC) initiated from a double-ended guillotine break may affect further operation of a High Temperature Gas Cooled Rector (HTGR), thorough understanding of each specific stage of this event is required. Key considerations that need to be determined is the amount of...
Resource Type:: Dissertation

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

Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

Creator:: Utberg, John E., Jr
Abstract:: The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...
Resource Type:: Masters Thesis

ScholarsArchive@OSU

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

Development of a Novel MEMS Thermal Sensor Array for Pebble Bed HTGRs

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

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

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

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

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

Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor

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

Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

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