Fabrication and characterization of LiH ceramic pebbles by wet process

Lithium hydride (LiH) ceramic pebbles, a new potential tritium breeding material in fusion–fission or fusion reactor blanket, were prepared by wet process for the first time. XRD results showed that LiOH, LiOH·H2O, Li2CO3 and Li2O were found in the surface of LiH pebbles. However, the pure phase of...

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Veröffentlicht in:Journal of nuclear materials 2014-09, Vol.452 (1-3), p.343-347
Hauptverfasser: Xiang, Maoqiao, Zhang, Yingchun, Hong, Ming, Liu, Zhiang, Leng, Jiaxun, Zhang, Yun, Zhang, Jialiang, Wang, Wenchang
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container_end_page 347
container_issue 1-3
container_start_page 343
container_title Journal of nuclear materials
container_volume 452
creator Xiang, Maoqiao
Zhang, Yingchun
Hong, Ming
Liu, Zhiang
Leng, Jiaxun
Zhang, Yun
Zhang, Jialiang
Wang, Wenchang
description Lithium hydride (LiH) ceramic pebbles, a new potential tritium breeding material in fusion–fission or fusion reactor blanket, were prepared by wet process for the first time. XRD results showed that LiOH, LiOH·H2O, Li2CO3 and Li2O were found in the surface of LiH pebbles. However, the pure phase of LiH pebbles without cracks could be obtained by paraffin wax coating technique. The average value (a.v.) of the sphericity and the diameter were 1.01 and 0.98mm, respectively. The LiH pebbles sintered at 450°C for 3h under 80ml/min flowing argon, reached ∼92.3% of the theoretical density, with the grain size of 5.59μm (a.v.). And the crush load was measured to be 15N on average. The described wet process exhibited multiple advantages for fabricating LiH pebbles.
doi_str_mv 10.1016/j.jnucmat.2014.05.065
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source ScienceDirect Journals (5 years ago - present)
subjects Ceramics
Cracks
Grain size
Lithium hydrides
Nuclear engineering
Paraffin wax
Shape
Theoretical density
title Fabrication and characterization of LiH ceramic pebbles by wet process
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