Thermal-hydraulic analysis of HCCB test blanket system

被引：4
|
作者：
Wang, Xiaoyong [1 ]
Zhang, Hongxiang [1 ]
Wu, Xinghua [1 ]
Ye, Xingfu [1 ]
Wang, Yanling [1 ]
Zhou, Bing [1 ]
Wang, Xiaoyu [1 ]
机构：
[1] Southwestern Inst Phys, Chengdu 610041, Sichuan, Peoples R China
来源：
FUSION ENGINEERING AND DESIGN | 2019年 / 138卷 / 352-357期
关键词：
ITER HCCB-TBS; Helium coolant system; TBM; Thermal-hydraulic performance; TBM;
D O I：
10.1016/j.fusengdes.2018.12.040
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
Understanding the thermal-hydraulic performance during international thermonuclear experimental reactor (ITER) plasma operation is compulsory for the test blanket module (TBM) and helium coolant system (HCS). Based on the design of the current TBM and HCS, one-dimensional thermal-hydraulic models for both the TBM and HCS have been created using the dynamic process simulation software APROS. Thermal-hydraulic performance analyses were conducted for steady and transient state during ITER plasma operation. The calculated results, including parameter distribution, parameter change during transient plasma operation, and relevant temperature control processes were investigated in detail. The results will provide critical support for the design and optimization of the TBM and HCS, including optimization of the equipment parameters, instrumentation and control design, interlock design, and safety design.
引用
收藏
页码：352 / 357
页数：6
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