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Tokamak discharge simulation coupling free-boundary equilibrium and plasma model with application to JT-60SA
Nuclear Fusion ( IF 3.5 ) Pub Date : 2021-01-16 , DOI: 10.1088/1741-4326/abcdb7
V. Ostuni 1 , J.F. Artaud 1 , G. Giruzzi 1 , E. Joffrin 1 , H. Heumann 2 , H. Urano 3
Affiliation  

In order to simulate a full tokamak discharge, a fast integrated tokamak modeling tool for scenario design, METIS, is coupled with a quasi-static free-boundary magnetic equilibrium code, FEEQS. The first code is able to compute at each time the plasma equilibrium, the current density and plasma pressure profiles. The generated outputs are iteratively used by the second code that computes the poloidal field coils currents needed in order to obtain a given plasma shape. This is used to assess the feasibility of scenarios designed by integrated modeling simulations. This approach is much faster with respect to full simulators, equipped with specific feedback controllers, and can be regarded as complementary or preparatory to much more time-consuming scenario control optimisation. The results obtained with the equilibrium code are benchmarked with data already available and computed using the TOSCA code. To illustrate how the coupled codes work, the optimization of one of the reference scenarios of the JT-60SA tokamak is carried out. The use of this new simulation tool for tokamak scenario design is discussed.



中文翻译:

托卡马克放电模拟结合自由边界平衡和等离子体模型及其在JT-60SA中的应用

为了模拟完整的托卡马克放电,用于场景设计的快速集成托卡马克建模工具METIS与准静态自由边界磁平衡代码FEEQS耦合。第一个代码能够每次计算血浆平衡,电流密度和血浆压力曲线。生成的输出由第二代码迭代使用,该第二代码计算为获得给定等离子体形状所需的多极场线圈电流。这用于评估通过集成建模仿真设计的方案的可行性。相对于配备有特定反馈控制器的完整模拟器而言,这种方法要快得多,并且可以被视为补充或为费时得多的场景控制优化做准备。用平衡代码获得的结果以已经可用的数据作为基准,并使用TOSCA代码进行计算。为了说明耦合的代码如何工作,对JT-60SA托卡马克的一种参考方案进行了优化。讨论了如何将这种新的仿真工具用于托卡马克方案设计。

更新日期:2021-01-16
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