Spherical tokamak assesses the potential of great performance in high beta and is capable of steadystate operation. Controlling plasma parameters and profile could lead to a high beta for spherical tokamaks. In this paper, we used the scaling laws of density, beta ratio, and energy confinement time with D-³He fuel. We investigated the dependency of Q on confinement enhancement factor and fuel density ratio of D-³He by plasma power balance equation in spherical tokamak (ST) which H _y2 ≈ 1.9 and f _D3 = 0.84 would lead to Q = 5.5 and high power production about 1.6 GW in the 65 keV. Hot ion mode as an imperative circumstance in ST has been investigated and we have illustrated that the convenient ion temperature is around 60–70 keV and γ ≈ 0.15–0.3 in order to enhance the operation of ST and restrict radiation loss.

球形托卡马克评估了高贝塔性能的潜力，并且能够稳定运行。控制等离子体参数和轮廓可能会导致球形托卡马克的高贝塔系数。在本文中，我们使用了 D- ³ He 燃料的密度、β 比和能量限制时间的标度定律。我们通过球形托卡马克 (ST) 中的等离子体功率平衡方程研究了Q对约束增强因子和 D- ³ He燃料密度比的依赖性，其中H _{y 2} ≈ 1.9 和f _{D 3} = 0.84 将导致Q = 5.5 并且在 65 keV 下产生约 1.6 GW 的高功率。已经研究了热离子模式作为 ST 中必不可少的情况，我们已经说明方便的离子温度约为 60-70 keV 和γ ≈ 0.15-0.3，以增强 ST 的操作并限制辐射损失。