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Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels

Creator:

Robinson, Cheryl A.

Abstract:

Through a joint effort by the Swiss Federal Institute for Reactor Research and Oregon State University, the fuels modeling code SPECKLE is being developed to model sphere-pac mixed carbide nuclear fuel. Major parameters, such as fission gas release, fuel restructuring phenomena, and the temperature and porosity distributions in the fuel...

Resource Type:

Masters Thesis

Full Text:

of Master of Science in Nuclear Engineering presented on July 6, 1981 Title: Burnup Dependent
Nodal methods for calculating nuclear reactor transients, control rod patterns, and fuel pin powers

Creator:

Cho, Byung-Oh

Abstract:

Nodal methods which are used to calculate reactor transients, control rod patterns, and fuel pin powers are investigated. The 3-D nodal code, STORM, has been modified to perform these calculations. Several numerical examples lead to the following conclusions: (1) By employing a thermal leakage-to-absorption ratio11 (TLAR) approximation for the spatial...

Resource Type:

Dissertation