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Filtering by: Creator Willison, James Stuart Subject Nuclear fuel rods -- Mathematical models

Thermal conductivity modeling of unrestructured sphere pac nuclear fuels

Creator:

Willison, James Stuart

Abstract:

In order to properly model the temperature distribution of a nuclear fuel pin, the thermal conductivity of the fuel must be known. For sphere pac fuel, the modeling of the conductivity is complicated due to the fact that the fuel is a collection of spheres in a random packed bed....

Resource Type:

Masters Thesis