کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
271965 | 505009 | 2010 | 6 صفحه PDF | دانلود رایگان |
Transport of tritium (T) and heat is calculated to estimate the performance of liquid Li17Pb83 (Li–Pb) or Li2BeF4 (Flibe) as a T-breeder in a fusion reactor blanket. T is bred in such a way of low leak to facilities outside and continuous recovery by a removal system, and heat is transferred through structural walls to He coolant efficiently. In this paper, T permeation in a blanket composed of structural materials and liquid Li–Pb or Flibe is calculated based on data of previous experiment. The effects of T recovery ratio by the outside removal apparatus and fluid-film T diffusion resistance in the liquid blanket on overall T permeation rates are analytically clarified. Design of a liquid blanket with low T leak and high T recovery is discussed here. In addition, possibility in that microbubbles may be generated at interfaces between a liquid blanket and a structural wall is investigated.
Journal: Fusion Engineering and Design - Volume 85, Issues 7–9, December 2010, Pages 1314–1319