INDENTATION FATIGUE OF CERAMIC NUCLEAR-FUELS

被引:2
|
作者
KUTTY, TRG
机构
[1] Radiometallurgy Division, Bhabha Atomic Research Centre, Bombay
关键词
D O I
10.1007/BF00714055
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The possibility of using an indentation technique for the determination of fatigue behaviour of sintered ceramic nuclear fuel pellets has been explored. A relation between load and number of cycles to failure has been derived. The underlying principle of this technique has also been explained. © 1990 Chapman and Hall Ltd.
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页码:455 / 458
页数:4
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