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Progress in extending high poloidal beta scenarios on DIII-D towards a steady-state fusion reactor and impact of energetic particles

41

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39

References

2020

Year

Abstract

To prepare for steady-state operation of future fusion reactors (e.g. the International Thermonuclear Experimental Reactor and China Fusion Engineering Test Reactor (CFETR)), experiments on DIII-D have extended the high poloidal beta (<em>β</em><SUB>P</SUB>) scenario to reactor-relevant edge safety factor <em>q</em><SUB>95</SUB> ~ 6.0, while maintaining a large-radius internal transport barrier (ITB) using negative magnetic shear. Excellent energy confinement quality (<em>H</em><SUB>98y2</SUB> > 1.5) is sustained at high normalized beta (<em>β</em><SUB>N</SUB> ~ 3.5). This high-performance ITB state with Greenwald density fraction near 100% and <em>q</em><SUB>min</SUB> ≥ 3 is achieved with toroidal plasma rotation <em>V</em><SUB>tor</SUB> ~ 0 at <em>ρ</em> ≥ 0.6. This is a key result for reactors expected to have low <em>V</em><SUB>tor</SUB>. At high <em>β</em><SUB>P</SUB> (≥1.9), large Shafranov shift can stabilize turbulence leading to a high confinement state with a low pedestal and an ITB. At lower <em>β</em><SUB>P</SUB> (<1.9), negative magnetic shear in the plasma core contributes to turbulence suppression and can compensate for reduced Shafranov shift to continue to access a large-radius ITB and excellent confinement with low <em>V</em><SUB>tor</SUB>, consistent with the results of gyrofluid transport simulations. These high-<em>β</em><SUB>P</SUB> cases are characterized by weak/no Alfvén eigenmodes (a.e.) and classical fast-ion transport. At high density, the fast-ion deceleration time decreases and Δ<em>β</em><SUB>fast</SUB> is lower; these reduce a.e. drive. The reverse-shear Alfvén eigenmodes are weaker or stable because the negative magnetic shear region is located at higher radius, away from the peaked fast-ion profile. Resistive wall modes can be a limitation at simultaneous high <em>β</em><SUB>N</SUB>, low internal inductance, and low rotation. Analysis suggests that additional off-axis external current drive could provide a more stable path at reduced <em>q</em><SUB>95</SUB>. Based on a DIII-D high-<em>β</em><SUB>P</SUB> plasma with large-radius ITB, two scenarios are proposed for CFETR <em>Q</em> = 5 steady-state operation with ~1 GW fusion power: a lower-$l_i$($l_i$ ~ 0.66) and a higher-$l_i$($l_i$ ~ 0.75) case. Using a Landau closure model, multiple energetic particle (EP) effects on the a.e. stability are analyzed modifying the growth rate of the a.e.s triggered by the neutral-beam-injection EPs and alpha particles, although the stabilizing/destabilizing effect is weak for the cases analyzed. The stabilizing effects of the combined EP species <em>β</em>, energy, and density profile in CFETR need further investigation.

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