Turbulence-driven cross-field transport of heat, particles, and momentum that dominates over collisional predictions and sets the actual size and cost of fusion reactors.
From the earliest tokamak experiments, measured energy and particle losses across magnetic field lines exceeded the predictions of collisional (classical and neoclassical) theory by factors of ten to one hundred. This excess, termed “anomalous transport,” was recognized as turbulence-driven by the 1970s, but quantitative prediction remained elusive for decades. The practical consequence is stark: anomalous transport determines the energy confinement time τE, which in turn dictates the plasma volume, magnetic field strength, and ultimately the capital cost required to reach ignition.1
Anomalous transport is sourced by a zoo of drift-wave micro-instabilities that feed on the free energy stored in plasma gradients. Ion temperature gradient (ITG) modes, driven by the radial gradient of ion temperature, typically dominate ion-channel heat loss. Trapped electron modes (TEM) tap into density and electron temperature gradients through the dynamics of magnetically trapped electrons. Electron temperature gradient (ETG) modes operate at smaller scales and contribute to the persistently high electron heat transport observed even when ion transport is suppressed to neoclassical levels.2
A defining feature of anomalous ion heat transport is “profile stiffness.” Above a critical normalized temperature gradient (R/LTi)crit, the turbulent heat flux increases so rapidly with gradient steepening that the profile is effectively clamped. Additional heating power raises the temperature at the boundary (pedestal) rather than steepening the core gradient. This stiffness behavior, confirmed by perturbative transport experiments and gyrokinetic simulations, explains why H-mode edge barrier physics has such outsized leverage on overall confinement.3
Breaking stiffness—through reversed magnetic shear, strong E×B flow shear, or shaping-induced stabilization—is the physics basis for advanced tokamak and spherical torus scenarios that aim to surpass standard scaling and achieve reactor-relevant confinement at reduced size.4