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Current status and challenges of key physics related to high-confinement operational scenarios and energetic particle confinement are briefly reviewed from the perspective of design and operation of tokamak-based fusion reactors. In the past few decades, significant progress has been made in the research on high-confinement mode physics, i.e. the main stability and confinement constraints on operational window of a fusion reactor have been identified, and some control methods for adjusting plasma kinetic profiles to optimize performance have been developed. Several operational scenarios, including inductive, hybrid and steady-state etc, which are potentially applicable for future reactors, have been developed. In the conditions that fusion alpha particle self-heating is predominant and shear Alfvén wave (SAW) instabilities potentially dominate fusion alpha particle transport, the SAW linear stability properties and excitation mechanisms are understood in depth, and the SAW instabilities nonlinear saturation, alpha particle confinement, and the influence of the heating deposition and the micro-turbulence regulation on fusion profile are under extensive investigation. The magnetically confined fusion research has entered a new stage of ignition and burning plasma physics, and new challenges that are faced are addressed, including whether efficient self-heating of plasmas by fusion alpha particles can be achieved, how the plasma stability and high-confinement can be maintained through the active control of key plasma profiles under the condition of dominant alpha particle heating, and whether it is possible to establish accurate models to predict long time scale complex dynamical evolution of fusion plasmas etc. Solving these key problems will lay a solid scientific foundation for designing and operating future fusion reactors as well as promote the development of plasma science.
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Keywords:
- magnetically confined fusion /
- tokamak /
- burning plasma physics /
- scenario
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图 1 托卡马克聚变堆运行的归一化参数区($q_{95}^{-1},\beta_{\rm N} $)示意图, 其中不同曲线代表一个理想的聚变堆需要满足的不同等离子体物理限制条件的示意分布, 如最低聚变功率需求(蓝色曲线), 稳定性极限限制(红色曲线), 最低聚变增益因子需求限制(绿色曲线)和高能量粒子约束限制(紫色曲线), 以及其他一些限制条件(灰色虚线)等
Figure 1. A schematic plot of operational window of a tokamak fusion reactor in terms of normalized parameters ($q_{95}^{-1},\beta_{\rm N}$). Different constraints from plasma physics for a fusion reactor, e.g. threshold fusion power (blue curve), stability limit (red curve), threshold fusion gain (green curve), limits from a particle confinement (purple curve), and some other constraints (gray dashed curves) etc.
图 3 ITER混合运行模式下阿尔芬连续谱和不稳定性示意图, 其中, 横坐标是归一化的径向位置, 纵坐标是频率, 虚线为安全因子分布, EPM表示高能量粒子模, TAE表示环阿尔芬本征模, EAE表示椭圆形变诱发阿尔芬本征模, NAE表示三角形变诱发阿尔芬本征模, 此处取环向模数n = 10
Figure 3. A schematic plot of shear Alfvén wave continuous spectrum and associated instabilities of ITER hybrid scenario is presented. Here, the horizontal axis represents the normalized minor radius, and the vertical axis is the normalized frequency. The dashed curve corresponds to the q-profile, and a representative toroidal mode number n = 10 is adopted. The frequencies and mode localizations of energetic particle mode (EPM), toroidal Alfvén eigenmode (TAE), ellipticity induced Alfvén eigenmode (EAE) and non-circularity induced Alfvén eigenmode (NAE) are also given.
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