A Zirconium-Cobalt Compound as the Material for a Reversible Tritium Getter
- 9 May 1986
- journal article
- research article
- Published by Taylor & Francis in Fusion Technology
- Vol. 9 (3) , 506-509
- https://doi.org/10.13182/fst86-a24739
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.Keywords
This publication has 4 references indexed in Scilit:
- Supply and recovery of hydrogen isotopes in high vacuum systems using ZrNi hydride getter pumpsJournal of Vacuum Science & Technology A, 1985
- Standard Gibbs energy and standard enthalpy of formation of UH3 from 450 to 750 KThe Journal of Chemical Thermodynamics, 1980
- An investigation of the systems ZrCo-H2 and ZrCo0.84Ni0.16H2Journal of the Less Common Metals, 1980
- A study of ZrCo and related ternary phases represented by the general formula, Zr50Co50 − xNixJournal of the Less Common Metals, 1974