Implanted deuterium retention and release in carbon-coated beryllium

被引:10
作者
Anderl, RA
Longhurst, GR
Pawelko, RJ
Oates, MA
机构
[1] Idaho National Engineering Laboratory,
关键词
fusion; beryllium; tritium; coatings; mobilization; experiments;
D O I
10.1023/A:1022569130666
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Deuterium implantation experiments have been conducted on samples of clean and carbon-coated beryllium. These studies entailed preparation and characterization of beryllium samples coated with carbon thicknesses of 100, 500, and 1000 Angstrom. Heat treatment of a beryllium sample coated with carbon to a thickness of approximately 100 Angstrom revealed that exposure to a temperature of 400 degrees C under high vacuum conditions was sufficient to cause substantial diffusion of beryllium through the carbon layer, resulting in more beryllium than carbon at the surface. Comparable concentrations of carbon and beryllium were observed in the bulk of the coating layer. Higher than expected oxygen levels were observed throughout the coating layer as well. Samples were exposed to deuterium implantation followed by thermal desorption without exposure to air. Differences were observed in deuterium retention and postimplantation release behavior in the carbon-coated samples as compared with bare samples. For comparable implantation conditions (sample temperature of 400 degrees C and an incident deuterium flux of approximately 6 X 10(19) D/m(2)-s), the quantity of deuterium retained in the bare sample was less than that retained in the carbon-coated samples. Further, the release of the deuterium took place at lower temperatures for the bare beryllium surfaces than for carbon-coated beryllium samples.
引用
收藏
页码:95 / 100
页数:6
相关论文
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