偏滤器物理设计与实验研究

应用B2-code模拟了偏滤器等离子体行为,优化了HL-2A装置偏滤器位形。研究了偏滤器刮削层中等离子体与器壁间过渡鞘层的离子碰撞效应,模拟研究了利用LHCD和NBI控制等离子体剖面分布在HL-2A中建立准稳态的反磁剪切位形。HL-2A装置首次实现了下单零点的偏滤器位形运行,完成了偏滤器初步物理实验,截至2004年底,获得等离子体电流320 kA,等离子体存在时间1 580 ms,环向磁场2.2 T。开展了高功率密度聚变堆偏滤器靶板的设计研究,特别是流动液态锂偏滤器靶板表面的物理过程的研究。探索性研究了用RF有质动力势改善偏滤器排灰效率和减少氚投料量。对FEB- E聚变堆偏滤器进行了优化设计。用电子束模拟对碳基材料及钨进行了高热负荷冲击实验,完成了钨/铜合金的热等静压焊接及热疲劳试验研究。研究了氦在钨中的滞留与热解吸行为。

Physics Design and Experimental Study of Tokamak Divertor

The divertor configuration of HL-2A tokamak is optimized,and the plasma performance in divertor is simulated with B2-code.The effects of collisionality on plasma-wall transition in the scrape-off layer of divertor are investigated, high performances of the divertor plasma in HL-2A are simulated,and a quasi- stationary RS operation mode is established with the plasma controlled by LHCD and NBI.HL-2A tokamak has been successfully operated in divertor configuration.The major parameters:plasma current I_p=320 kA,toroidal field B_t=2.2 T,plasma discharger duration T_d=1 580 ms ware achieved at the end of 2004.The preliminary experimental researches of advanced diverter have been carried out.Design studies of divertor target plate for high power density fusion reactor have been carried out,especially,the physical processes on the surface of flowing liquid lithium target plate.The exploration research of improving divertor ash removal efficiency and reducing tritium inventory resulting from applying the RF ponderomotive force potential is studied.The optimization structure design studies of FEB-E reactor divertor are performed. High flux thermal shock experiments were carried on tungsten and carbon based materials.Hot Isostatic Press (HIP) method was employed to bond tungsten to copper alloys.Electron beam simulated thermal fatigue tests were also carried out to W/Cu bondings.Thermal desorption and surface modifica- tion of He~ implanted into tungsten have been studied.