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Lithium divertor concept and results of supporting experiments

机译：锂分压器的概念和支持实验的结果

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The ITER project development has shown that considerable difficulties are encountered when already known engineering solutions and materials are used for divertor and divertor plates for tokamaks of such a scale. We offer to use a Li capillary-pore system (CPS) as a plasma facing material for tokamak divertor. Evaporated Li serves as a gas target and redistributes thermal load. The heat flux from the plasma is transported to the first wall by Li radiation in the plasma periphery. This allows the divertor plate to reduce the heat flux. A solid CPS filled with liquid lithium has a high resistance to surface damage in the stationary mode and during plasma transitions (disruptions, ELMS, VDEs, runaways) to assure normal operation of the divertor target plates. These materials are not the sources of impurities giving rise to Z(eff) and they will not be collected as dust in the divertor area and in ducts. Experiments with lithium CPS in a steady-state mode (up to 25 MW m(-2)) and in plasma disruption simulation conditions (similar to5 MJ m(-2), similar to0.5 ms) have been performed. High stability of these systems have been shown. Li limiter tests on T-11M tokamak have revealed the lithium CPS compatibility with the edge plasma for energy loads of up to 10 MW m(-2). In a stable discharge mode at lithium limiter temperature of 20-600degreesC, no Li abnormal erosion and injection to plasma have been detected. A high sorption of D+ and H+ ions on the vessel walls was the main substantial result of the replacement of a graphite limiter by lithium one. He and D sorption was terminated by wall heating up to 50-100degreesC and above 350degreesC, respectively. T-11 tests on helium discharge allowed to reduce limiter heat load by a factor of two due to lithium radiation. All the experimental results have shown considerable progress in the development of lithium divertor. [References: 44]
机译：国际热核实验堆项目的发展表明，当将已知的工程解决方案和材料用于这种规模的托卡马克的分流板和分流板时，会遇到相当大的困难。我们提供使用锂毛细管孔系统（CPS）作为托卡马克分流器的面向等离子体的材料。蒸发的锂用作气体目标并重新分配热负荷。来自等离子体的热通量通过等离子体外围中的Li辐射传输到第一壁。这允许分流板减小热通量。填充有液态锂的固态CPS在固定模式下和等离子转变（破裂，ELMS，VDE，失控）期间具有很高的抗表面损伤能力，以确保分流器目标板的正常运行。这些材料不是产生Z（eff）的杂质来源，它们也不会作为灰尘收集在分流器区域和管道中。在稳态模式（最高25 MW m（-2））和等离子体破坏模拟条件（类似于5 MJ m（-2），类似于0.5 ms）下进行了锂CPS的实验。这些系统具有很高的稳定性。在T-11M托卡马克上进行的锂限制器测试表明，对于能量负载高达10 MW m（-2）而言，锂CPS与边缘等离子体的相容性。在锂限制器温度为20-600摄氏度的稳定放电模式下，未检测到Li异常腐蚀和等离子体注入。 D +和H +离子在容器壁上的高吸附是用锂限制剂代替石墨限制剂的主要实质结果。通过分别加热至50-100℃和350℃以上来终止He和D的吸附。通过进行T-11氦气排放测试，由于锂辐射，可以将限制器的热负荷降低两倍。所有的实验结果都表明锂偏滤器的发展取得了长足的进步。 [参考：44]

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