摘要
随着HL-3装置的运行参数逐渐提升,第一壁结构需承受的热负荷也逐渐增加,尤其是NBI穿透等离子体后的残余功率直接打击的第一壁,其区域的平均热负荷将达到1 MW·m^(-2)以上,持续时间5 s。基于热传导和对流换热方程,利用正交试验方法对高热负荷区影响传热性能的第一壁的石墨厚度、热沉板厚度、流道直径以及界面接触热阻等关键传热结构设计变量进行了数值计算和参数优化研究。结果表明,对于HL-3装置脉冲等离子体运行来说,上述4个参数均与第一壁表面温度呈负相关。同时,石墨厚度变量对碳基第一壁传热结构性能影响最大,其次是石墨与热沉板间的界面接触传热系数变量,而热沉板316L厚度与管道冷却直径对它的影响较小。
Following the plasma parameters of the HL-3 tokamak gradually improving,the thermal loads that the first wall needs to withstand also gradually increase,especially the residual power of the first wall at the neutral beam shine-through area would be more than 1.0 MW·m^(-2) and duration 5 s.Based on the thermal conduction and the convective heat transfer equations,numerical simulation and parameters optimization were conducted on key first wall structural design variables influencing the heat transfer performance,such as the graphite thickness,heat sink plate thickness,flow channel diameter and thermal contact conductance between combined surfaces in the high flux zones,using the orthogonal experimental technique.The results indicate that the above four factors are reversely correlated with the surface temperature of first wall for HL-3 tokamak pulsed plasma operation.Besides,the graphite thickness is the greatest impact on the heat transfer performance of the carbon-based first wall,followed by the thermal contact conductance between the graphite and the heat sink plate,while the thickness of the heat sink plate 316L and the cooling pipe diameter are relatively low impact on that.
作者
卢勇
蔡立君
刘健
许婕
栗再新
刘晓龙
赵周
HL-3第一壁团队
LU Yong;CAI Li-jun;LIU Jian;XU Jie;LI Zai-xin;LIU Xiao-long;ZHAO Zhou;HL-3 First Wall Team(Southwestern Institute of Physics,Chengdu 610041)
出处
《核聚变与等离子体物理》
北大核心
2025年第4期373-380,共8页
Nuclear Fusion and Plasma Physics
基金
四川省自然科学基金项目(2022NSFSC1196)
西物创新项目(202301XWCX005-04)。
关键词
托卡马克
正交设计
第一壁
传热分析
Tokamak
Orthogonal design
First wall
Thermal transfer analysis
