HT-7U装置纵场线圈的稳态及瞬态传热分析  

Thermal analysis of toroidal field coils of the HT-7U tokamak

作　　者：陈文革[1] 李登啸[2] 潘引年[1] 武松涛[1] 翁佩德[1] 

机构地区：[1]中国科学院等离子体物理研究所,安徽合肥230031 [2]合肥工业大学机械与汽车工程学院,安徽合肥230009

出　　处：《合肥工业大学学报（自然科学版）》2001年第4期517-522,共6页Journal of Hefei University of Technology：Natural Science

摘　　要：文章分析了 TH- 7U托卡马克核聚变装置在正常和非正常运行情况下产生的各种热负荷在纵场磁体上的热行为 ,给出了纵场线圈盒最严重部位上的温度分布云图 ,计算过程考虑了核热沉积、各种热传导、热辐射、涡流损耗热和迫流式超临界氦进行对流换热等过程。针对等离子体快速破裂时 ,在极短的时间内 ,其纵场磁体中产生的较大涡流损耗而引起的焦耳热对纵场线圈盒与超导磁体之间的热传递过程加以研究。该文采用国际上较为流行的有限元分析软件 COSMOS/ M进行计算 ,由于简化了纵场线圈有限元分析模型及真实情况下部分热流量的不确定性 ,所得结果较为乐观 ,但这些结果对 HT- 7U装置的工程设计仍具有重要意义。The thermal behavior of the toroidal field(TF) coil in HT 7U has been investigated in normal and abnormal operation conditions. The detailed temperature map in the most critical cooling paths for TF case has been computed, considering the heat influxes due to nuclear heating, conduction, radiation,and eddy currents for the case and the heat removal through the forced flow supercritical helium. In this paper, the thermal analysis is made of the particular status of a plasma disruption. During the disruption, a significant amount of energy is deposited in the case, so particular attention is paid to the heat transfer between the case and the winding. The magnitude and the location of temperature distribution are mostly determined by using the code of COSMOS/M. The simplifications in the finite element(FE) model of TF coil and the uncertainties in the heat influx are possible to lead to optimistic results, but these results are valuable for some engineering designs.

关 键 词：HT-7U核聚变装置 纵场线圈 瞬态传热 稳态传热 对流换热 温度分布 

分 类 号：TL612.11[核科学技术—核技术及应用]