Graphite and Xenon Behavior and their Influence on Molten-Salt Reactor Design
作者:
ScottDunlap,
EatherlyW. P.,
期刊:
Nuclear Applications and Technology
(Taylor Available online 1970)
卷期:
Volume 8,
issue 2
页码: 179-189
ISSN:0550-3043
年代: 1970
DOI:10.13182/NT70-A28624
出版商: Taylor&Francis
数据来源: Taylor
摘要:
Existing data an dimensional changes in graphite have been fitted to parabolic temperature-sensitive curves. From these, the graphite life, radiation-induced stresses, and permissible geometries have been calculated. It is concluded existing materials can be utilized in a molten-salt reactor which has a core graphite life of about four years, without serious cost penalty.Fission product xenon can be removed by sparging the fuel salt with helium bubbles and removing them after enrichment. With reasonable values of salt-to-bubble transfer coefficient and graphite permeability, the penalty to breeding ratio can be reduced to<0.5%.
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