Integrated Modelling for Steady State Spherical Tokamaks
Integrated Modelling for Steady State Spherical Tokamaks
复制标题
稳态球形托卡马克集成建模
DOI：
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发表时间：
2003
期刊：
影响因子：
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通讯作者：
A. Kirk
中科院分区：
文献类型：
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作者：
J. Connor;J. Ahn;R. Akers;J. Christiansen;G. Counsell;A. Dnestrovskij;M. Hole;A. Kirk
基于球形托卡马克(ST)方法的聚变电站(PP)的发展首先需要证明一个自洽的稳态解。在这篇文章中，我们考虑了涉及的各种物理问题，并强调了综合理论建模如何有助于确保这些单独元素的解的一致性。我们关注的是长宽比R/a=1.4(R是环面的大半径，a是等离子体的小半径)，它接近系统代码[1]所预测的经济型聚变电厂的最佳值。稳定状态运行的关键要求是有效的无感电流驱动(CD)方案。这通过高自举电流分数FBS来缓解，所述高自举电流分数FBS通过高极向等离子体POL例如通过接近极限操作并利用高伸长率来实现。然而，这必须与对各种MHD模式的稳定性一致，从而限制CD的径向轮廓。人们可以通过组合不同的CD方案来满足这些要求。
The development of a fusion power plant (PP) based on the spherical tokamak (ST) approach first requires the demonstration of a self-consistent steady state solution. In this paper we consider the various physics issues involved and emphasise how integrated theoretical modelling can help to ensure the consistency of the solutions to these individual elements. We focus on an aspect ratio R/a = 1.4 (R is the major radius of the torus, a the plasma minor radius) which is close to an optimum for an economic fusion power plant predicted by systems codes [1]. The key requirement for stead y state oper ation is an efficient non-inductive current drive (CD) scheme. This is mitig ated by a high bootstrap current fraction, fbs, achieved through high poloidal plasma , pol, e.g. by operating close to the -limit, and exploiting high elongation, . However this must be consistent with stability to various MHD modes, constraining the radial profile of the CD. One can satisfy these by a combination of different CD schemes.