Index Catalog // ScholarsArchive@OSU

Creator:: Anderson, Michael Jay
Abstract:: Pressurized water reactors are presently controlled by the use of materials which absorb neutrons as their only effect; this reduces the neutron economy of the system, since these neutrons are lost without helping to maintain the chain reaction. The system examined in this study replaces these absorbing materials with a...
Resource Type:: Masters Thesis
Full Text:: pressurized water reactors AN ABSTRACT OF THE THESIS OF Michael J. Anderson for the degree of Master of

Creator:: Luo, Shyr Tung
Abstract:: A detailed formulation of the momentum equation including the Baroczy model for two phase friction is presented in this thesis. Numerical techniques for solving this equation along with the remainder of the describing equations are also presented. This model has been incorporated into an existing thermal hydraulic code for simulating...
Resource Type:: Masters Thesis
Full Text:: itself, the steam generator is one of the principal components in a pressurized water reactor (PWR

Creator:: Chadly, Peter Brent
Abstract:: A vital safety concern in the analysis of nuclear power reactors is the thermal hydraulic behavior of the reactor coolant system under steady state and transient conditions. The goal of this study has been to develop an appropriate model for the U-tube type steam generators in a typical pressurized water...
Resource Type:: Masters Thesis
Full Text:: a pressurized water reactor AN ABSTRACT OF THE THESIS OF Peter B. Chadly for the degree of Master

Creator:: Antoine, Stephanie Y. L. Antoine
Abstract:: This research presents an analysis of thermal stratification in the reactor cold leg of the Advanced Plant Experiment-Combustion Engineering (APEX-CE). This phenomenon may be a precursor leading to a Pressurized Thermal Shock (PTS) event in a nuclear power plant. This work was performed in support of the U.S. Nuclear Regulatory...
Resource Type:: Masters Thesis
Full Text:: Loop Water in Pressurized Water Reactor Cold Legs" [10], Sun et al. studied the phenomenon of

Creator:: Almarshad, Abdullah I. A.
Abstract:: A model has been developed to predict the long-term oxidation rate of Zircaloy-4 for ex-reactor (autoclave) and in-reactor (PWR) environments and operating conditions. A computer program has been written to solve the oxygen diffusion equation by employing a fully implicit finite difference method for a one dimensional cylindrical geometry. The...
Resource Type:: Dissertation
Full Text:: model to predict long-term waterside corrosion weight gain and oxide thickness in pressurized water

Creator:: Davis, Ian M. (Ian Mack)
Abstract:: Benchmark calculations are performed for neutron transport in a two material (binary) stochastic multiplying medium. Spatial, angular, and energy dependence are included. The problem considered is based on a fuel assembly of a common pressurized water nuclear reactor. The mean chord length through the assembly is determined and used as...
Resource Type:: Masters Thesis
Full Text:: a fuel assembly of a common pressurized water nuclear reactor. The mean chord length through the

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