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

Takanori Nagasaki, Satoshi Konishi, Hiroji Katsuta, Yuji Naruse

Fusion Science and Technology / Volume 9 / Number 3 / Pages 506-509

May 1986

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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.

 
 
 
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