Preliminary structural design and thermo-mechanical analysis of helium cooled solid breeder blanket for Chinese Fusion Engineering Test Reactor
Preliminary structural design and thermo-mechanical analysis of helium cooled solid breeder blanket for Chinese Fusion Engineering Test Reactor
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DOI：
10.1016/j.fusengdes.2014.12.011
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发表时间：
2015-02
影响因子：
1.7
通讯作者：
Min Li;Hongli Chen;Guangming Zhou;Qianwen Liu;Shuai Wang;Z. Lv;M. Ye
中科院分区：
文献类型：
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作者：
Min Li;Hongli Chen;Guangming Zhou;Qianwen Liu;Shuai Wang;Z. Lv;M. Ye
为了弥补ITER和核聚变电厂之间的研发差距，中国核聚变工程试验堆（CFETR）被提议在中国建造。CFETR的任务是解决实现实用聚变能的基本研发问题。它的覆盖层需要氚自给自足。本文设计并分析了采用多层u型卵石层的氦冷却固体增殖包层。在正常运行稳态条件下，对与增殖机组结合的第一壁和侧壁进行了热力学分析。结果表明，结构材料、中子倍增器和氚增殖球床的最高温度分别为523℃、558℃和787℃，低于550℃、650℃和920℃的极限。结构的最大等效应力低于许用值，差值约为14.5%。
With the aim to bridge the R&D gap between ITER and fusion power plant, the Chinese Fusion Engineering Test Reactor (CFETR) was proposed to be built in China. The mission of CFETR is to address the essential R&D issues for achieving practical fusion energy. Its blanket is required to be tritium self-sufficient. In this paper, a helium cooled solid breeder blanket adopting multilayer U-shaped pebble beds was designed and analyzed. Thermo-mechanical analysis of the first wall and side wall combined with breeder unit was carried out for normal operating steady state conditions. The results showed that the maximum temperatures of the structural material, neutron multiplier and tritium breeder pebble beds are 523 °C, 558 °C and 787 °C, respectively, which are below the corresponding limits of 550 °C, 650 °C and 920 °C. The maximum equivalent stress of the structure is under the allowable value with a margin about 14.5%.