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作 者:王佳琪 蒙建鹏 贾瑞宝 刘晓龙[1] 李强[1] 陈鑫[1] 颉延风[1] WANG Jia-qi;MENG Jian-peng;JIA Rui-bao;LIU Xiao-long;LI Qiang;CHEN Xin;XIE Yan-feng(Southwestern Institute of Physics,Chengdu 610041)
出 处:《核聚变与等离子体物理》2024年第4期401-408,共8页Nuclear Fusion and Plasma Physics
基 金:西物创新(202102XWCXRZ001)。
摘 要:利用COMSOL Multiphysics软件对HL-3装置环向场线圈(TF)进行了热工水力分析,研究了不同工况下线圈的冷却效率,得到了冷却水的压力、流量及温度分布情况。分析结果表明,TF线圈的冷却时间控制在900s内完全可以满足装置的冷却需求。在140kA和190kA电流的条件下,一次通电周期内线圈的最高温度不会超过80℃,不会对线圈之间的匝间绝缘造成破坏。TF线圈的主要发热集中在中心柱段,在对线圈施加冷却措施下,600s时线圈的温度可以降到较低的范围,900s时可以使线圈得到充分的冷却。线圈内部管道中的冷却水流速控制在2~4m·s^(-1)较为合适,入口压力不宜超过0.45MPa。在必要的情况下,可以将TF线圈的冷却时间减少至600s。The thermal analysis on the toroidal field coil of HL-3 tokamak is carried out by using COMSOL Multiphysics software.The cooling efficiency of the coil under different working conditions is studied,and the pressure,flow rate and temperature distribution of cooling water are obtained.The results show that the cooling time of toroidal field(TF)coil controlled within 900s can fully meet the requirements of the device.Under the condition of 140kA and 190kA flat top current,the maximum temperature of the coil in one discharge will not exceed 80℃,which will not damage the inter turn insulation between the coils.The main heat generation of TF coil is concentrated in the central post section.When cooling is applied to the coil,the temperature of the coil after 600s can be reduced to a lower range,and the coil can be fully cooled after 900s.The flow rate of cooling water in the internal pipe of the coil should be controlled at 2~4m·s^(-1),and the inlet pressure cannot exceed 0.45MPa.The cooling time of TF coil can be reduced to 600s.
分 类 号:TL622[核科学技术—核技术及应用]
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