Index Catalog // ScholarsArchive@OSU

Kinetics of the decomposition of organic reactor coolants

Creator:: De Halas, Don Richard
Resource Type:: Dissertation
Full Text:: properties enable the con- struction of a nuclear reactor without the high pressure piping and expensive

A study of buoyant backflow in vertical injection lines

Creator:: King, John Barry
Abstract:: In the event of a small break loss of coolant accident (SBLOCA) in a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to compensate for the coolant loss. When this flow rate is less than a critical value, however, the hot fluid in the cold...
Resource Type:: Dissertation
Full Text:: a nuclear reactor, cold fluid is injected through the reactor system high pressure injector to

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

Creator:: Goodrich, Sam S.
Abstract:: In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
Resource Type:: Dissertation
Full Text:: engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent

Quantified PIRT and uncertainty quantification for computer code validation

Creator:: Luo, Hu
Abstract:: This study is intended to investigate and propose a systematic method for uncertainty quantification for the computer code validation application. Uncertainty quantification has gained more and more attentions in recent years. U.S. Nuclear Regulatory Commission (NRC) requires the use of realistic best estimate (BE) computer code to follow the rigorous...
Resource Type:: Dissertation
Full Text:: procedures to rule reactor Emergency Core Cooling System (ECCS) analysis in 10CFR50.46 and Appendix K in

Nuclear Power Plant Siting in the Columbia River Basin: Current Trends, Effects of Climate Change, and Associated Uncertainties

Creator:: Savotkina, Alexandra A.
Abstract:: This PhD dissertation describes and evaluates a geographical analysis of candidate areas for siting nuclear plants utilizing a wet cooling tower in the Columbia River Basin (CRB). It focuses on the analysis of water availability for cooling and how it may be limited by climate change effects on river streamflow....
Resource Type:: Dissertation
Full Text:: of candidate areas for siting nuclear plants utilizing a wet cooling tower in the Columbia River

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

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

Performance and stability analysis of gas-injection enhanced natural circulation in heavy-liquid-metal-cooled systems

Creator:: Yoo, Yeon-Jong
Abstract:: The purpose of this study is to investigate the performance and stability of the gas-injection enhanced natural circulation in heavy-liquid-metal-cooled systems. The target system is STAR-LM, which is a 400-MWt-class advanced lead-cooled fast reactor under development by Argonne National Laboratory and Oregon State University. The primary loop of STAR-LM relies...
Resource Type:: Dissertation
Full Text:: considered to be linearly stable, especially for the conventional nuclear reactor designs where the

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

Kinetics of the decomposition of organic reactor coolants

A study of buoyant backflow in vertical injection lines

Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

Quantified PIRT and uncertainty quantification for computer code validation

Nuclear Power Plant Siting in the Columbia River Basin: Current Trends, Effects of Climate Change, and Associated Uncertainties

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

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

Performance and stability analysis of gas-injection enhanced natural circulation in heavy-liquid-metal-cooled systems

A computer control algorithm for a nuclear reactor support system

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