摘要
根据中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)包层背板的设计方案及具体的包层模块内部工况,分别完成了对高场侧包层背板和低场侧包层背板的流道的设计。背板的内部流道具体包括两根吹扫气体流道、三根冷却剂冷流道、三根冷却剂热流道。通过ANSYS软件中的FLUENT模块来初步模拟仿真包层背板的固体和流体热工基本情况,分别得到了背板在200 MW、500 MW、1 GW和1.5 GW工况下的温度场分布及各流道内部流体的热交换情况。结果表明:高场侧背板和低场侧背板的最高温度均小于结构材料的许用温度;高场侧和低场侧内部流道的冷却剂平均温度变化均符合包层端入口和出口的设计要求。
[Background]Blanket is an important component of China fusion engineering test reactor(CFETR).A large amount of heat inside the blanket needs to bring coolant to the outside of the Tokamak device.[Purpose]This study aims to design the channel of inboard(IB)and outboard(OB)back supporting structure(BSS)to suitable for multiple operating conditions.[Methods]The thermal analyses for BSS under four working conditions were performed by FLUENT,a computational fluid dynamics(CFD)software,which conducted by fluid-solid coupling finite element.The temperature distribution and the heat exchange of IB,OB BSS under 200 MW,500 MW,1 GW and 1.5 GW conditions were analyzed.[Results]The temperature distribution of the BSS,the heat exchange of the internal fluid and the average temperature change of the fluid were obtained under four working conditions.[Conclusion]The maximum temperature of the IB BSS and the OB BSS is less than the allowable temperature of the structural material;the average temperature change of the coolant on the IB and OB channels is consistent with the blanket outlet and inlet.
作者
吴琪刚
刘素梅
雷明准
徐坤
黄卫
WU Qigang;LIU Sumei;LEI Mingzhun;XU Kun;HUANGWei(School of Mechanical Engineering,Anhui University of Science and Technology,Huainan 232000,China;Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,China)
出处
《核技术》
CAS
CSCD
北大核心
2019年第9期73-80,共8页
Nuclear Techniques
基金
中国聚变工程实验堆集成工程设计研究项目(No.2017YFE0300500)资助~~
关键词
包层背板
流道
热工分析
Blanket back supporting structure
Channel
Thermal analysis