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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。
The B2-code was used to simulate the behavior of the divertor plasma and to optimize the divertor configuration of the HL-2A unit. The ion impact effect of the transition sheath between the plasma and the wall in divertor scraper was studied. The quasi-steady diamagnetic shear configuration of HL-2A was simulated by LHCD and NBI controlled plasma profile distribution. For the first time, the HL-2A device realized the position operation of the divertor with a single order zero point. The preliminary physical experiment of the divertor was completed. By the end of 2004, the plasma current of 320 kA, the plasma presence time of 1 580 ms and the toroidal magnetic field of 2.2 T were obtained. The design of divertor targets for high power density fusion reactor has been carried out. In particular, the physical process of the surface of the fluid lithium divertor target has been studied. Exploratory research has been carried out to improve the ash discharge efficiency of the divertor and reduce the amount of tritium feed by using RF momentum. The FEB-E fusion stack divertor has been optimized. Electron beam simulation of carbon-based materials and tungsten high thermal load impact experiments completed tungsten / copper alloy hot isostatic pressing welding and thermal fatigue test. The retention and thermal desorption behavior of helium in tungsten were investigated.