Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1567610 | Journal of Nuclear Materials | 2010 | 6 Pages |
Abstract
Lithium-containing ceramics have long been recognized as the tritium breeding materials in the fusion-fission or fusion reactor blanket. Li3TaO4 (lithium orthotantalate) pebbles, with high melting point (â¼1406 °C), good thermal stability, and high thermal conductivity, were fabricated by wet process (freeze-drying) as a new potential candidate of tritium breeder. The diameter of ceramic pebbles is 0.7-1.0 mm, density is over 90% (TD), pore diameter is 1.86 μm (a.v), grain size is 15 μm (a.v), crush load is up to 46.7 N (a.v).
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Zhu Deqiong, Peng Shuming, Chen Xiaojun, Gao Xiaoling, Yang Tongzai,