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Achievement of a high-density, high-confinement, and high-beta tokamak plasma regime in DIII-D, and implications for a lower-current path for ITER and FPP

Experiments on DIII-D have demonstrated a density-confinement synergy that enables sustainment of high performance in a previously unattained parameter regime of simultaneous very high energy confinement quality (H<sub>98y2</sub> ≥ 1.5), very high line-average density Greenwald fraction (ƒ<sub>Gr</sub> = πa<sup>2</sup>&lt; n &gt;/I<sub>P</sub> ≥ 1.4), and high toroidal beta (β<sub>T</sub> ≥ 3%). Tokamak operation in this regime is essential for a compact steady-state FPP, as well as for Q=10 with 500 MW of fusion power in ITER at I<sub>P</sub> &lt;&lt; 15 MA. These experiments leveraged the knowledge that, in the high-poloidal-beta (β<sub>P</sub>) regime, impurity and density gradients can enhance turbulence stabilization caused by high α<sub>MHD</sub> (α<sub>MHD</sub>~(dβ<sub>P</sub>)⁄dr). This was described by theoretical predictions and gyrokinetic transport simulations [M.T. Kotschenreuther et al, 2024 Nucl. Fusion, 64 076033], and later confirmed by experiments on DIII-D [S. Ding et al, 2024 Nature 629 555]. To increase both β<sub>P</sub> and β<sub>T</sub>, the new experiments increased the ideal-wall stability β<sub>N</sub>-limit by using a smaller plasma-outer wall distance and higher triangularity in the plasma cross section (top/bottom average δ~0.9), enabled by the recent “shape &amp; volume rise” (SVR) modification to the DIII-D divertor. The higher triangularity also contributed to achieving higher ƒ<sub>Gr</sub> by enabling higher pedestal density. At high density, the pedestal is ballooning limited and exhibits small and frequent ELMs, while the divertor is near detachment even without any impurity seeding. High plasma performance was attained and sustained reproducibly, with the eventual terminations brought about by an MHD mode destabilized as the current profile slowly continued to evolve. A path to stationary fully noninductive operation might include ECH injection to reduce both core impurity accumulation and the electron collisionality, thus increasing the bootstrap current. These experiments provide the first experimental demonstration of the ƒ<sub>Gr</sub>, H<sub>98y2</sub>, and β<sub>T</sub> values required simultaneously for ITER Q = 10 at I<sub>P</sub> &lt; 10 MA, pointing to practical ways to improve the energy confinement in a fusion reactor.

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Experiments on DIII-D have demonstrated a density-confinement synergy that enables sustainment of high performance in a previously unattained parameter regime of simultaneous very high energy confinement quality (H<sub>98y2</sub> ≥ 1.5), very high line-average density Greenwald fraction (ƒ<sub>Gr</sub> = πa<sup>2</sup>&lt; n &gt;/I<sub>P</sub> ≥ 1.4), and high toroidal beta (β<sub>T</sub> ≥ 3%). Tokamak operation in this regime is essential for a compact steady-state FPP, as well as for Q=10 with 500 MW of fusion power in ITER at I<sub>P</sub> &lt;&lt; 15 MA. These experiments leveraged the knowledge that, in the high-poloidal-beta (β<sub>P</sub>) regime, impurity and density gradients can enhance turbulence stabilization caused by high α<sub>MHD</sub> (α<sub>MHD</sub>~(dβ<sub>P</sub>)⁄dr). This was described by theoretical predictions and gyrokinetic transport simulations [M.T. Kotschenreuther et al, 2024 Nucl. Fusion, 64 076033], and later confirmed by experiments on DIII-D [S. Ding et al, 2024 Nature 629 555]. To increase both β<sub>P</sub> and β<sub>T</sub>, the new experiments increased the ideal-wall stability β<sub>N</sub>-limit by using a smaller plasma-outer wall distance and higher triangularity in the plasma cross section (top/bottom average δ~0.9), enabled by the recent “shape &amp; volume rise” (SVR) modification to the DIII-D divertor. The higher triangularity also contributed to achieving higher ƒ<sub>Gr</sub> by enabling higher pedestal density. At high density, the pedestal is ballooning limited and exhibits small and frequent ELMs, while the divertor is near detachment even without any impurity seeding. High plasma performance was attained and sustained reproducibly, with the eventual terminations brought about by an MHD mode destabilized as the current profile slowly continued to evolve. A path to stationary fully noninductive operation might include ECH injection to reduce both core impurity accumulation and the electron collisionality, thus increasing the bootstrap current. These experiments provide the first experimental demonstration of the ƒ<sub>Gr</sub>, H<sub>98y2</sub>, and β<sub>T</sub> values required simultaneously for ITER Q = 10 at I<sub>P</sub> &lt; 10 MA, pointing to practical ways to improve the energy confinement in a fusion reactor.

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