中国电机工程学报2012，Vol.32Issue(26)：91-95,5.
聚变堆实验包层模块第一壁传热结构优化分析
Heat Transfer Structure Optimization Analysis for the First-wall of Fusion Power Reactor
摘要
Abstract
Controlled nuclear fusion has been considered as the optimal energy to human beings. Test blanket module is a critical component of the international thermal experimental reactor. There are two designs for the first-wall of Chinese helium-cooled solid breeder test blanket module (CH HCSB TBM). One has 3 coolant pipelines and the other has 5. On the basis of simplifying both designs, combined with convection heat transfer calculation, the temperature distribution of the first-wall was achieved and the design of four coolant pipelines was proposed. The allowable temperature of 5 coolant pipelines is 5"C lower than that of 3 coolant pipelines. The specific structure of 4 coolant pipelines has a 13 mm radical size and a 13.5 mm longitudinal size. Compared with the previous two schemes, this one has the lower temperature distribution as well as larger temperature safety allowance. Additionally, it is with more economy of more material than the three pipelines ones.关键词
核聚变/实验包层/第一壁/传热/温度/结构Key words
nuclear fusion/ test blanket/ first-wall/ heat transfer/ temperature/ structure分类
能源科技引用本文复制引用
周涛,刘梦影,廖航涛,苏子威..聚变堆实验包层模块第一壁传热结构优化分析[J].中国电机工程学报,2012,32(26):91-95,5.基金项目
中国科学院战略性先导科技专项资助(XDA03040000). （XDA03040000）
