Abstract
Experimental and modeling investigations on the DIII-D and EAST tokamaks show the attractive transport and stability properties of fully noninductive, high poloidal-beta (β P ) plasmas, and their suitability for steady-state operating scenarios in ITER and CFETR. A key feature of the high-β P regime is the large-radius (ρ > 0.6) internal transport barrier (ITB), often observed in all channels (ne, Te, Ti, rotation), and responsible for both excellent energy confinement quality and excellent stability properties. Experiments on DIII-D have shown that, with a large-radius ITB, very high β N and β P values (both ≥ 4) can be reached by taking advantage of the stabilizing effect of a nearby conducting wall. Synergistically, higher plasma pressure provides turbulence suppression by Shafranov shift, leading to ITB sustainment independent of the plasma rotation. Experiments on EAST have been used to assess the long pulse potential of the high-β P regime. Using RF-only heating and current drive, EAST achieved minute-long fully noninductive steady state H-mode operation with strike points on an ITER-like tungsten divertor. Improved confinement (relative to standard H-mode) and steady state ITB features are observed with a monotonic q-profile with q min ∼ 1.5. Separately, experiments have shown that increasing the density in plasmas driven by lower hybrid wave broadens the q-profile, a technique that could enable a large radius ITB. These experimental results have been used to validate MHD, current drive, and turbulent transport models, and to project the high-β P regime to a burning plasma. These projections suggest the Shafranov shift alone will not suffice to provide improved confinement (over standard H-mode) without rotation and rotation shear. However, increasing the negative magnetic shear (higher q on axis) provides a similar turbulence suppression mechanism to Shafranov shift, and can help devices such as ITER and CFETR achieve their steady-state fusion goals.
Original language | English |
---|---|
Article number | 014043 |
Journal | Plasma Physics and Controlled Fusion |
Volume | 60 |
Issue number | 1 |
DOIs | |
State | Published - Jan 2018 |
Externally published | Yes |
Funding
This material is based upon work supported in part by the US Department of Energy, Office of Science, Office of Fusion Energy Sciences DE-FC02-04ER546981, (Cooperative Agreement No. DE-SC00106851 and Contract Nos. DE-SC-00104923, DE-FG02-01ER546154), DE-AC02-09CH114665, DE-AC52-07NA273446, and by the National Magnetic Confinement Fusion Program of China (Nos. 2015GB1020022, 2015GB1030002).
Funders | Funder number |
---|---|
US Department of Energy | |
Office of Science | |
Fusion Energy Sciences | DE-AC02-09CH114665, DE-AC52-07NA273446, DE-FG02-01ER546154, DE-SC-00104923, DE-FC02-04ER546981 |
National Magnetic Confinement Fusion Program of China | 2015GB1030002, 2015GB1020022 |
Keywords
- ITB
- high bootstrap current
- steady state
- tokamak