Index Catalog // ScholarsArchive@OSU

Creator:: Skeen, David Roy
Abstract:: Because of the high cost of fuel for nuclear reactors, fuel cycle costs must be predicted accurately. This leads to the high cost computer computations and a search for cheaper yet still accurate methods. For this paper we have chosen to study an alternate method for calculating thermal neutron cell...
Resource Type:: Dissertation
Full Text:: studies are expensive. For an example, let us examine a fuel management program. A typical reactor fuel

Creator:: Abdul-hamid, Shahab A.
Abstract:: Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...
Resource Type:: Masters Thesis
Full Text:: is uniformly mixed in the fuel. MCNPBURN was benchmarked using a standard Pressurized Water Reactor

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:: oxide formed on the waterside surface of 132 reactor-irradiated rods with various fuel burnups. The

Creator:: Al-Kheliewi, Abdullah S.
Abstract:: A transient code (TFETC) for calculating the temperature distribution throughout the radial and axial positions of a thermionic fuel element (TFE) has been successfully developed. It accommodates the variations of temperatures, thermal power, electrical power, voltage, and current density throughout the TFE as a function of time as well as...
Resource Type:: Dissertation
Full Text:: , where t is a reactor transient time in seconds, the fuel temperature does not exceed the melting

Creator:: Brice, Derek J.
Resource Type:: Masters Thesis
Full Text:: criticality calculations In the past, anticipating prompt fuel reprocessing, it used to be that heat

ScholarsArchive@OSU