It is a touchstone for the success of ITER and future fusion reactor whether the present high performance negative-ion-based NBI (N-NBI) heating systems work properly. The LHD and JT-60U are only two facilities where N-NBI systems are working for high power plasma heating / current drive in the world. Because handling of negative hydrogen / deuterium ions was amateur technology, it has taken a long time to improve its skill. In LHD, we succeeded in improving the performance of one of three beam lines dramatically in 2003 by adopting a multi-slot grounded grid for the accelerator of ion source. The effort on improving the performance was also done in other beam lines with conventional ion sources in parallel. The guidelines of improving are optimization of magnetic multi-cusp configuration for efficient negative ion production, and increasing the transparency of the grounded grid for reduction of heat load on it. As a result the available beam power has been increased, that is, successive injection power level more than 10MW became possible throughout four-month long experimental campaign, although the maximum injection power has been almost the same. The averaged negative ion beam current density at the exit of ion source, which was evaluated from the port-through injected power, was achieved up to 350A/m^2 up0 nosupersub which is larger than the required value of ITER NBI in hydrogen beam operation. Pulse length at high beam power level has also been extended owing to the reduction of heat load on the grounded grid. These results (increase in available power and pulse length) have contributed to expand the operation region of LHD. By continuous R&D, we also have found the way of solving an associated problem of multi-slot grounded grid system, that is, mismatched conditions of optimum beam optics in vertical and horizontal directions. According to this result, better beam divergence can be realized, and the increase in the total injection power is expected in the next experimental campaign.
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机译:当前的高性能基于负离子的NBI(N-NBI)加热系统是否正常运行,是ITER和未来聚变反应堆成功的试金石。 LHD和JT-60U仅是N-NBI系统在世界上用于大功率等离子体加热/电流驱动的两个设施。由于处理负氢/氘离子是业余技术,因此花了很长时间来提高其技能。在LHD中,我们在2003年通过采用多槽接地栅格作为离子源加速器,成功地显着改善了三根束线之一的性能。在与常规离子源平行的其他束线中也进行了提高性能的工作。改进的准则是优化磁性多尖端结构以有效产生负离子,并增加接地格栅的透明度以减少其上的热负荷。结果,尽管最大注入功率几乎相同,但在整个四个月的实验过程中,可用的射束功率有所增加,也就是说,连续注入功率水平可能超过10MW。通过端口注入的功率估算出的离子源出口处的平均负离子束电流密度高达350A / m ^ 2 up0 nosupersub,大于氢束运行中ITER NBI的要求值。由于减少了接地电网上的热负荷,因此在高波束功率水平下的脉冲长度也得到了扩展。这些结果(增加可用功率和脉冲长度)有助于扩大LHD的工作范围。通过持续的研发,我们还找到了解决多槽接地栅格系统相关问题的方法,即在垂直和水平方向上最佳光束光学系统的不匹配条件。根据该结果,可以实现更好的光束发散,并且在下一个实验中有望提高总注入功率。
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