Abstract
Abstract The utility of ZrCo for tritium storage has been studied and a comparison with uranium has been made. Loading, unloading, and delivery operations typically required in tritium handling loops were conducted using two identical beds: one containing 25.0 g of ZrCo and the other 25.8 g of uranium powder. Hydrogen was the working gas. The two beds have similar performance characteristics although the bed containing uranium has faster loading kinetics and can attain a lower vacuum at room temperature. Particulates are transported into the loop by both beds and appear to be more difficult to contain in the ZrCo case. The temperature ramp rate to the unloading temperature for ZrCo must be controlled if operating at high H/M ratios. A transformation of the ZrCo alloy into a phase which has inferior loading rate characteristics may be induced by rapid temperature ramping.
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