Fabrication processes and testing of the moderator for irradiating devices of BN reactors. Testing of the moderator
-
Published:2020-12-01
Issue:1
Volume:1005
Page:012001
-
ISSN:1757-8981
-
Container-title:IOP Conference Series: Materials Science and Engineering
-
language:
-
Short-container-title:IOP Conf. Ser.: Mater. Sci. Eng.
Author:
Polunin K K,Mokrushin A A
Abstract
Abstract
The work presents the results of studies of zirconium hydride used as the moderator for irradiating devices in fast reactors. Zirconium hydride fabrication process using methods of direct saturation of the source material and powder preparation and compacting has been optimized. Hydrostatic method was used to measure density of the samples: for the samples produced by direct saturation density varies within 5.61 to 5.65 g/cm3, for compacted zirconium hydride - 5.45 to 5.55 g/cm3. Tests to evaluate hydrogen release from zirconium hydride have been conducted. It has been shown that dehydration onset temperature is (420 – 450) °C (powder compaction method) and (500 – 550) °C (direct saturation method). It has been noted that in 20 minutes of the sample heating from 500 to 900 °C, the mass fraction of the hydrogen released is 0.6 %. The results acquired confirm the data on diminished thermal stability of zirconium hydride produced by the powder method in gaseous media.
Cited by
1 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. Raman spectroscopy of zirconium hydride;Journal of Nuclear Materials;2024-05