MECHANICAL-PROPERTIES OF IRRADIATED BERYLLIUM

被引:20
作者
BEESTON, JM [1 ]
LONGHURST, GR [1 ]
WALLACE, RS [1 ]
ABELN, SP [1 ]
机构
[1] EG&G ROCKY FLATS INC,GOLDEN,CO 80402
关键词
D O I
10.1016/0022-3115(92)90366-S
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Beryllium is planned for use as a neutron multiplier in the tritium breeding blanket of the International Thermonuclear Experimental Reactor (ITER). After fabricating samples of beryllium at densities varying from 80 to 100% of the theoretical density, we conducted a series of experiments to measure the effect of neutron irradiation on mechanical properties, especially strength and ductility. Samples were irradiated in the Advanced Test Reactor (ATR) to a neutron fluence of 2.6 x 10(25) n/m2 (E > 1 MeV) at an irradiation temperature of 75-degrees-C. These samples were subsequently compression-tested at room temperature, and the results were compared with similar tests on unirradiated specimens. We found that the irradiation increased the strength by approximately four times and reduced the ductility to approximately one fourth. Failure was generally ductile, but the 80% dense irradiated samples failed in brittle fracture with significant generation of fine particles and release of small quantities of tritium.
引用
收藏
页码:102 / 108
页数:7
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