Abstract
The effect of the intermittent passage of gas bubbles entrained in the sodium coolant on the integrity of the fuel rod cladding is examined for typical conditions of liquid metal fast breeder reactors. The maximum stable size of the bubbles is calculated to be of the order of 0.5 in equivalent spherical diameter. The transient blanketing of the fuel rod due to the passage of the bubbles is studied for two extremely conservative geometrical configurations. The maximum calculated cladding temperature increase during the transient was found to be fairly limited, and the thermal fatigue effect due to the passage of a large number of bubbles was assessed. It appears that even in the most pessimistic conditions the fatigue effect is well below the failure limit. It has been concluded, therefore, that gas bubbles flowing through the core do not endanger the cladding integrity and do not reduce the fuel rod lifetime.
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