A Zirconium-Cobalt Compound as the Material for a Reversible Tritium Getter

Abstract

An intermetallic compound of zirconium-cobalt was prepared, and the pressure-composition isotherms for the ZrCo-H system were measured in the pressure range from 10 Pa (0.1 Torr) to ∼130 kPa (1000 Torr) and in the temperature range from 130 to 400°C. The equilibrium hydrogen pressures of plateaus under the experimental conditions were one or two orders of magnitude higher than that of a uranium-hydrogen system. A pronounced hysteresis between hydrogenating isotherms and dehydrogenating ones was observed. Based on the results, ZrCo is proposed as a substitute for uranium for the purpose of recovering, storing, and supplying gaseous tritium.