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Lithium metazirconate for nuclear application: physical and mechanical properties

✍ Scribed by L. Montanaro; A. Negro; J. P. Lecompte


Book ID
104739390
Publisher
Springer
Year
1995
Tongue
English
Weight
656 KB
Volume
30
Category
Article
ISSN
0022-2461

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✦ Synopsis


Lithium metazirconate is a candidate in fusion reactor designs as a tritium-breeding material. An amorphous powder was synthesized by gelling zirconium propylate and lithium acetate: after heat treatment at 900 ~ pure Li2ZrOa-I was obtained. Preliminary tests made on sintered pellets, obtained from this powder, demonstrated an appropriate tritium release at low temperature, when the sample porosity was about 20% and the mean pore radius 3 gm. The subject of this paper was to realize a good compromise between mechanical properties and the spread porosity, necessary for tritium diffusion. Dilatometric investigations were performed on compacts of powders treated at 800, 900 and 1000~ to identify the best temperature and time of sintering. The calcined powders were also uniaxially pressed at 200, 300 and 500 MPa: the green bodies were sintered at 1200, 1250 and 1300~ for 2 or 4 h, in order to produce ceramics having different porosity. On the sintered bodies, the pore size distribution, the mean pore radius and mechanical properties were evaluated.


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