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Conduction in a Nuclear Fuel Rod

Fuel Pin simulator including simulated uranium dioxide fuel pellets and Zircalloy clad enclosing them. Courtesy Areva
UPDATED: 09/16/2022

The workbook calculates the temperature distribution due to conduction in a geometry representative of a nuclear fuel rod.   This analytical solution includes volumetric heat generation from nuclear fission in the rod itself and contact resistance at the gap between the fuel pin and its cladding.  Beyond that is conductive resistance of the Zircaloy cladding and convective resistance (=1/hA) at the outer surface, where it is bathed by coolant.

Temperature as a function of radius in a Pressurized Water Reactor (PWR) fuel rod. The profile is convex up, as expected, in the heat generating zone. Next there is a temperature drop across the fuel-clad interface.  That if followed by another across the clad and a third representing the convective resistance.

Note the calculated temperature drop of some 1600K over a distance of about half a centimeter.  Certainly, the change in thermal conductivity must be included.

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