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Two-dimensional resistive MHD simulation of the optimized plasma formation in the spherical tokamaks
Nuclear Fusion ( IF 3.5 ) Pub Date : 2021-04-23 , DOI: 10.1088/1741-4326/abebce
T. Ahmadi 1 , H. Tanabe 2 , Y. Ono 2
Affiliation  

We present 2D global MHD simulation results of the optimized start-up scenarios for the spherical tokamak to maximize the ion heating energy determined by the value of the poloidal private flux during the merging start-ups. The series of simulations has successfully revealed the dependence of the poloidal private flux on the in-vessel poloidal coils’ separation length under the fixed amount of coils’ magnetic energy. The radial and azimuthal locations of the internal coils need to be optimized to maximize high private flux and consequently high ion heating energy. In the case of a two poloidal field (PF) coils system, the private flux and ion heating energy increase with the coils’ separation length. Installing two additional PF coils improves the private flux significantly, even if the coils’ separation length is short.



中文翻译:

球形托卡马克中优化等离子体形成的二维电阻 MHD 模拟

我们展示了球形托卡马克优化启动场景的 2D 全局 MHD 模拟结果,以最大化在合并启动期间由极向私有通量值确定的离子加热能量。这一系列模拟成功地揭示了在线圈磁能固定的情况下,极向私磁通量对容器内极向线圈分离长度的依赖性。需要优化内部线圈的径向和方位角位置,以最大化高私有通量和高离子加热能量。在两个极向场 (PF) 线圈系统的情况下,私有通量和离子加热能量随着线圈的分离长度而增加。安装两个额外的 PF 线圈显着提高了私有磁通,即使线圈的分离长度很短。

更新日期:2021-04-23
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