COMPATIBILITY OF STAINLESS-STEELS AND LITHIATED CERAMICS WITH BERYLLIUM

被引:15
作者
FLAMENT, T
FAUVET, P
SANNIER, J
机构
[1] CEA, France
关键词
Beryllium and Alloys - Ceramic Materials - Neutrons - Nuclear Reactors; Breeder--Breeding Blankets - Stainless Steel;
D O I
10.1016/0022-3115(88)90297-8
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The introduction of beryllium as a neutron multiplier in ceramic blankets of thermonuclear fusion reactors may give rise to the following compatibility problems: (i) oxidation of Be by ceramics (lithium aluminate and silicates) or by water vapor; (ii) interaction between beryllium and austenitic and martensitic steels. The studies were done in contact tests under vacuum and in tests under wet sweeping helium. The contact tests under vacuum have revealed that the interaction of beryllium with ceramics seems to be low up to 700°C, the interaction of beryllium with steels is significant and is characterized by the formation of a diffusion layer and of a brittle Be-Fe-Ni compound. With type 316 L austenitic steel, this interaction appears quite large at 600°C whereas it is noticeable only at 700°C with martensitic steels.
引用
收藏
页码:496 / 499
页数:4
相关论文
共 7 条
[1]   THE HIGH TEMPERATURE OXIDATION OF BERYLLIUM .4. IN WATER VAPOUR AND IN MOIST OXYGEN [J].
AYLMORE, DW ;
GREGG, SJ ;
JEPSON, WB .
JOURNAL OF NUCLEAR MATERIALS, 1961, 3 (02) :190-200
[2]   THE HIGH TEMPERATURE OXIDATION OF BERYLLIUM AND THE FATE OF BERYLLIUM CARBIDE INCLUSIONS [J].
JEPSON, WB ;
WARBURTON, JB ;
MYATT, BL .
JOURNAL OF NUCLEAR MATERIALS, 1963, 10 (02) :127-133
[3]  
KITTEL JH, ANL4937129
[4]   THE COMPATIBILITY OF BERYLLIUM AND URANIUM DIOXIDE [J].
KNAPTON, AG ;
WEST, KBC .
JOURNAL OF NUCLEAR MATERIALS, 1961, 3 (02) :239-240
[5]  
NAIK MC, 1966, MEM ETUD SCI REV MET, V63, P488
[6]  
RASNEUR B, 1985, FUSION TECHNOL, V9, P1909
[7]   IMPROVED METHODS FOR FABRICATION OF LITHIUM SILICATES [J].
VOLLATH, D ;
WEDEMEYER, H ;
GUNTHER, E .
JOURNAL OF NUCLEAR MATERIALS, 1985, 133 (AUG) :221-225