Study of D-3He fusion fuel parameters sensitivity in spherical tokamak

Abstract

Abstract 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.