Index Catalog // ScholarsArchive@OSU

Effect of Initial Conditions and Depressurization on Lock Exchange Flow After a Depressurized Conduction Cool-Down Event in the High Temperature Test Facility

Creator:: Glass, Molly
Abstract:: The High Temperature Test Facility (HTTF) is an electrically heated, scaled model of a Modular High Temperature Gas Reactor (MHTGR). Five experiments were conducted to study Depressurized Conduction Cool-Down phenomena stemming from a Double-Ended Guillotine Break (DEGB). After a DEGB, the reactor pressure vessel would depressurize until the pressures are...
Resource Type:: Masters Thesis
Full Text:: of the policy was to determine the next generation nuclear plant. It is required that the reactor

Modeling and analysis of a heat transport transient test facility for space nuclear systems

Creator:: Wheeler, Adam
Abstract:: The purpose of this thesis is to design a robust test facility for a small space nuclear power system and model its physical behavior under different scenarios. The test facility will be used to simulate a 1-10kWe nuclear reactor, its electrical generation, and heat removal capabilities. This simulator will be...
Resource Type:: Masters Thesis
Full Text:: different scenarios. The test facility will be used to simulate a 1-10kWe nuclear reactor, its electrical

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

Creator:: Alberti, Anthony L.
Abstract:: With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
Resource Type:: Masters Thesis
Full Text:: - ment of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels

One and two dimensional space-energy flux synthesis with spatially discontinuous trial functions

Creator:: Olson, Willard Orvin
Abstract:: The development of nuclear reactors as an energy source requires a substantial investment in capital and effort. This development depends heavily on accurate calculational methods. Space-energy flux synthesis, also variously called the spectral synthesis method, modal method, and overlapping group method, is one possible method. In this method the energy...
Resource Type:: Dissertation
Full Text:: DOCTOR OF PHILOSOPHY (NaMe of'Student) (Degree) in Nuclear Engineering presented on (Major Department

Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles

Creator:: Park, Jin Yong
Abstract:: This thesis consists of two parts. Part I (Chapters 1, 2, 3) of this thesis concerns finding the best way of running a reactor whose catalyst decays with use, and must consequently be replaced or regenerated at regular intervals. Chapter 1 introduces the problem, and Chapter 2 develops a one...
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
Full Text:: started research and development into advanced nuclear reactor technologies. [1] Consequently, the

Development of an object-oriented expert system for PWR core reload

Creator:: Greek, Kevin J.
Abstract:: Reactor refueling is a computationally intensive problem solving process that requires automation since significant resources are expended upon the search for an optimal core loading. Without imposing some constraints upon the configurations investigated, an extremely large number of prototype loadings may be generated without discovery of an improved loading. As...
Resource Type:: Dissertation
Full Text:: Nuclear Engineering presented on December 12, 1989. Title: Development of an Object-Oriented Expert

Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

Creator:: Cox, Jordan
Abstract:: The United States (US) Department of Energy (DOE) has identified the pebble-bed reactor as a high priority for US research with the end goal of licensing a pebble-bed reactor (PBR) for operation in the United States. Before this can be accomplished significant research must be done regarding the safety of...
Resource Type:: Masters Thesis
Full Text:: of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High

Analysis of nuclear reactor period measurements

Creator:: Moon, Laurence Leslie
Resource Type:: Masters Thesis
Full Text:: Analysis of nuclear reactor period measurements ANALYSIS

A computer control algorithm for a nuclear reactor support system

Creator:: Kosorok, John Roger
Abstract:: The High Temperature Lattice Test Reactor (HTLTR) at Richland, Washington, operates at temperatures up to 1000°C. Its low nuclear power requires a 384 kilowatt electrical heating system, that is divided into four circuits, to attain the high temperatures in the ten-foot cube of moderating graphite. This thesis describes the design...
Resource Type:: Dissertation
Full Text:: A computer control algorithm for a nuclear reactor support

ScholarsArchive@OSU

Effect of Initial Conditions and Depressurization on Lock Exchange Flow After a Depressurized Conduction Cool-Down Event in the High Temperature Test Facility

Modeling and analysis of a heat transport transient test facility for space nuclear systems

Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

One and two dimensional space-energy flux synthesis with spatially discontinuous trial functions

Optimum operating cycle for systems with deactivating catalyst and the reaction of solid particles

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

Development of an object-oriented expert system for PWR core reload

Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

Analysis of nuclear reactor period measurements

A computer control algorithm for a nuclear reactor support system

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