热核反应堆包层材料气体释放的系统实验研究

IF 0.2 Q4 PHYSICS, MULTIDISCIPLINARY
J. A. Zaurbekova, S. Askerbekov, A. Shaimerdenov, E. V. Chihrai, A. Akhanov, G. Kizane
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引用次数: 0

摘要

结果表明,该装置可以在773-1473 K的温度下进行,并且可以在研究样品中氚和氦的工作水平高于10 -11 mol/s的情况下记录系统中的气体流量。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Methodical experiments on the study of gas release from materials of thermonuclear reactor blankets
which that from the of in-vestigated to the installation with partial recorded in the The of thermophysical and showed that with the developed can be carried out at temperatures of 773-1473 K and that the can register the gas flow in the system at the operating level of tritium and helium in the studied samples above 10 -11 mol/s.
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