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Uranium Dioxide-Cladding Interactions. Axial Expansion of UO2 Column in Fuel Elements

C. N. Spalaris

Nuclear Science and Engineering / Volume 17 / Number 3 / Pages 381-391

November 1963

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Irradiation experiments have been conducted to determine the axial expansion of UO2 in fuel elements. The experiments included fuel segments with 304 stainless and Zircaloy-2 sheaths in self-supporting tubular geometries under boiling water conditions, as well as fuel elements with 304 stainless UO2-supported geometries under superheated steam conditions. The relative UO2 expansion during irradiation was measured by mechanical devices included in the fuel segments and by visual and other observations.

 
 
 
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