Magnetic-Confinement Fusion—Plasma Theory: Tokamak Magnetohydrodynamic Equilibrium and Stability

MHD stability of negative triangularity DIII-D plasmas

“…An off-trend, spurious limit calculation has been removed from the time series presented. The Troyon limit on maximally attainable β N without a conducting wall can be empirically described by the expression β No wall N = kl i where k accounts for modifications to stability due to shaping and profile variation [31,32]. Scenarios with peaked current density profiles tend to see k ∼ 2.5 whereas scenarios' whose profiles are broader see k ∼ 4.…”

Magnetic Confinement Fusion—Development Facilities

“…magnet systems, H&CD systems, fuelling and impurity injection systems (Snipes et al, 2017). At high plasma performance, the control of magnetohydrodynamic (MHD) instabilities (Lao et al, 2020) is particularly critical in ITER to maintain the fusion burn and to avoid potential damage to the first wall. For example, edge localized modes (ELMs), which expel short bursts of heat and particles, are controlled by a set of 27 in-vessel copper coils (Vostner et al, 2019).…”

“…For example, edge localized modes (ELMs), which expel short bursts of heat and particles, are controlled by a set of 27 in-vessel copper coils (Vostner et al, 2019). Disruptions, which produce high transient heat and electromechanical loads on in-vessel structures, must be avoided or their effects mitigated (see Lao et al, 2020;Zohm, 2020). A dedicated system, based on fragmentation of cryogenic deuterium or noble gas pellets, and referred to as Shattered Pellet Injection, SPI (Lehnen et al, 2015) will operate under PCS control to implement disruption mitigation.…”