Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST

• Published in: Nuclear fusion 2017-06, Vol.57 (7), p.76037
• Main Authors: Garofalo, A.M., Gong, X.Z., Qian, J., Chen, J., Li, G., Li, K., Li, M.H., Zhai, X., Bonoli, P., Brower, D., Cao, L., Cui, L., Ding, S., Ding, W.X., Guo, W., Holcomb, C., Huang, J., Hyatt, A., Lanctot, M., Lao, L.L., Liu, H., Lyu, B., McClenaghan, J., Peysson, Y., Ren, Q., Shiraiwa, S., Solomon, W., Zang, Q., Wan, B.
• Format: Article
• Language: English
• Subjects: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; current profile control; lower hybrid; magnetic fusion; steady-state tokamak
• ISSN: 0029-5515; 1741-4326
• DOI: 10.1088/1741-4326/aa7186

Recent experiments on EAST have achieved the first long pulse H-mode (61 s) with zero loop voltage and an ITER-like tungsten divertor, and have demonstrated access to broad plasma current profiles by increasing the density in fully-noninductive lower hybrid current-driven discharges. These long pulse discharges reach wall thermal and particle balance, exhibit stationary good confinement (H98y2 ~ 1.1) with low core electron transport, and are only possible with optimal active cooling of the tungsten armors. In separate experiments, the electron density was systematically varied in order to study its effect on the deposition profile of the external lower hybrid current drive (LHCD), while keeping the plasma in fully-noninductive conditions and with divertor strike points on the tungsten divertor. A broadening of the current profile is found, as indicated by lower values of the internal inductance at higher density. A broad current profile is attractive because, among other reasons, it enables internal transport barriers at large minor radius, leading to improved confinement as shown in companion DIII-D experiments. These experiments strengthen the physics basis for achieving high performance, steady state discharges in future burning plasmas.