Power pulse meltdown experiments performed in the mark I TREAT sodium loop on clusters of 7 EBR-II Mark I type pins

Abstract Two experiments were performed on fuel failure and post-failure movements of fuel and coolant under power excursions. Test samples consisted of seven-pin clusters in instrumented integral sodium loops inserted into the TREAT reactor. One cluster was run with sodium flow and the other with pump power off (transient-induced flow could occur). Results agreed with the predictions of a simple calculational model of pin failure which had been tested previously in less elaborate experiments. Extensive post-failure movements of molten fuel occurred. Although sharp pressure spikes were recorded their magnitude is within a range that can be accommodated by reasonable engineering designs.

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