HT-7U石墨材料在HT-7超导托卡马克装置的先行实验

通过对1种新型石墨材料进行等离子体轰击实验，近似计算出材料的热导率大约为70W／m*K，石墨可以承受高达2.41MW／m2的能流密度(实验中最大值)。模头位置及波加热条件下，石墨受等离子体轰击程度的不同，主要与轰击粒子能量有关。在等离子体能量梯度方向改变石墨位置比增加等离子体能量更易达到大的能流轰击。石墨材料的抗轰击能力及抗溅射能力都比较好，在长时间等离子体轰击情况下，由石墨材料产生的杂质足够低，不影响等离子体放电，基本上满足装置正常运行的要求。

Study of HT-7U Graphite in HT-7 Superconducting Tokamak

A new type of graphite,which may sustain an energy flux of as high as 2.41 MW／m2(maximum value available)and whose thermal conductivity is apporximately 70 W／m*K,has been successfully developed to be used as HT-7U wall material in a plasma bombardment study.The changes in graphite sruface temperature were analyzed at various positions and in different heating modes.The preliminary results show that the graphite has good thermal shock resistance and high resistance to physical sputtering.In a long time bombardment of plasma,impurity levels remain to be low enough not to affect plasma discharge,which is important to ensure Tokamak routine operation.