Ideal MHD Stability of a Spherical Tokamak Power Plant and a Component Test Facility
|Title||Ideal MHD Stability of a Spherical Tokamak Power Plant and a Component Test Facility|
|Publication Type||Journal Article|
|Year of Publication||2010|
|Authors||Hole, MJ, Wilson, HR, Abeysuriya, R, Larson, JW|
|Journal||Plasma Physic. Control. Fusion|
We have investigated ideal MHD stability of two advanced spherical tokamak confinement concepts: the Spherical Tokamak Power Plant, a 3 GW concept fusion power plasma producing 1 GW of electric power, and the Component Test Facility, a concept designed for in situ materials testing for ITER and beyond. Detailed stability studies for toroidal mode number n = 1,2,3 displacements are presented as a function of conformal wall radius R[sub w] and on-axis safety factor q[sub 0]. These confirm that both concepts are stable provided that the wall is sufficiently close and q[sub 0] sufficiently large (q[sub 0] > 2.8 for the power plant and q[sub 0] > 2.1 for the component test facility). For the component test facility we have also extended earlier scans to study the marginal stability boundaries for constant plasma current I[sub p]. This work involved implementing parallel versions of the equilibrium transformation and stability scans. Both power plant and component test facility configurations are found to be ballooning stable.