Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor

被引：17

作者：

Lei, Mingzhun ^{[1
]}

Xu, Shuling ^{[1
]}

Guo, Chao ^{[1
]}

Liu, Sumei ^{[1
]}

Song, Yuntao ^{[1
]}

Lu, Kun ^{[1
]}

Pei, Kun ^{[1
]}

Xu, Kun ^{[1
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, POB 1126, Hefei 230031, Anhui, Peoples R China

来源：

INTERNATIONAL JOURNAL OF ENERGY RESEARCH | 2018年 / 42卷 / 04期

关键词：

CFETR; flow distribution; HCCB blanket; structure design; thermal hydraulic analysis; ITER;

D O I：

10.1002/er.3961

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

China Fusion Engineering Test Reactor, a fusion tokamak device, is proposed to provide complementary technology and experience for ITER and the future fusion power plant. A helium-cooled ceramic breeder blanket concept is adopted as the candidate tritium breeding blanket for China Fusion Engineering Test Reactor. Detailed design of the blanket structure located at the outboard equatorial plane is presented. The coolant flow characters in the blanket were calculated by the theoretical method and the finite element method. The comparison of the calculated results was done, and it has a good agreement between theoretical results and simulation results. The results show that the pressure drop is 0.13MPa and the total temperature rise is 194.6 degrees C.

引用

页码：1657 / 1663

页数：7

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