T. C. Hender

TL;DR: A review of recent advances in the area of MHD stability and disruptions, since the publication of the 1999 ITER Physics Basis document (1999 Nucl. Fusion 39 2137-2664), is reviewed in this paper.

TL;DR: In this paper, a set of external coils (A-coils) capable of producing nonaxisymmetric, predominantly n=1, fields with different toroidal phase and a range of poloidal mode m spectra has been used to determine the threshold amplitude for mode locking in Alcator C-Mod.

Abstract: Values of ${\ensuremath{\beta}}_{T}\ensuremath{\ge}30%$ have been achieved and sustained for several confinement times on the START spherical tokamak using additional heating provided by neutral beam injection. These values are more than twice the highest value previously obtained in a tokamak, and correspond to normalized $\ensuremath{\beta}$ values of ${\ensuremath{\beta}}_{N}\ensuremath{\ge}4$. In these shots values of ${I}_{p}g{I}_{\mathrm{rod}}$ (where ${I}_{\mathrm{rod}}$ is the current flowing in the central toroidal field rod) have been obtained, which are considered to be necessary for spherical tokamak power plant. The results are compared with ideal-MHD stability theory.

TL;DR: Menard et al. as mentioned in this paper developed a blanket system capable of tritium breeding ratio TBR ≈ 1, a poloidal field coil set supporting high elongation and triangularity for a range of internal inductance and normalized beta values consistent with NSTX/NSTX-U previous/planned operation, and a long-legged divertor analogous to the MAST-U divertor which substantially reduces projected peak divertor heat-flux and has all outboard field coils outside the vacuum chamber and superconducting to reduce power consumption.

TL;DR: In this paper, the separation of the cylindrical tearing mode stability problem into a resistive resonant layer calculation and an external marginal ideal magnetohydrodynamic (MHD) calculation (Δ' calculation) is generalized to axisymmetric toroidal geometry.