TY - JOUR
T1 - Active recycling control through lithium injection in EAST
AU - Canik, J. M.
AU - Sun, Z.
AU - Hu, J. S.
AU - Zuo, G. Z.
AU - Xu, W.
AU - Huang, M.
AU - Wang, L.
AU - Xu, J.
AU - Zhang, T.
AU - Maingi, R.
AU - Lunsford, R.
AU - Diallo, A.
AU - Mansfield, D.
AU - Osborne, T.
AU - Tritz, K.
N1 - Publisher Copyright:
© 1973-2012 IEEE.
PY - 2018/5
Y1 - 2018/5
N2 - The coating of tokamak walls with thin layers of lithium has been demonstrated to reduce plasma recycling from the plasma-facing surfaces and to improve overall plasma performance. These effects, including reduced divertor Dα emission, the elimination of edge-localized modes, and increased energy confinement have been observed in multiple experiments when lithium coatings are applied before plasma discharges. However, this coating technology does not extrapolate to future long-pulse devices, since the lithium coatings will be passivated by the continual plasma flux onto the surface. In order to provide active conditioning capability, a new technology has been developed that is capable of injecting lithium powder into the scrape-off layer plasma during plasma discharges, where it quickly liquefies and turns into an aerosol. The use of this 'lithium dropper' is under study at the Experimental Advanced Superconducting Tokamak (EAST), where the potential benefits of real-time wall conditioning via lithium injection are being tested. Here, we present an analysis of the recycling characteristics during EAST experiments testing active lithium injection in order to assess recycling reduction and control. Lithium aerosol was injected from the top of the machine, with one system dropping lithium near the X-point and another into the low-field side divertor leg. The injection of lithium into the SOL reduced divertor recycling, as evidenced by reduced Dα emission with ion flux measured by probes relatively unchanged. This effect is strongest in the active divertor, confirming the lithium is transported to strongly plasma-wetted areas. Quantitative analysis of the recycling changes using the SOLPS edge plasma and neutral transport code indicated a 20% reduction in recycling coefficient with lithium injection.
AB - The coating of tokamak walls with thin layers of lithium has been demonstrated to reduce plasma recycling from the plasma-facing surfaces and to improve overall plasma performance. These effects, including reduced divertor Dα emission, the elimination of edge-localized modes, and increased energy confinement have been observed in multiple experiments when lithium coatings are applied before plasma discharges. However, this coating technology does not extrapolate to future long-pulse devices, since the lithium coatings will be passivated by the continual plasma flux onto the surface. In order to provide active conditioning capability, a new technology has been developed that is capable of injecting lithium powder into the scrape-off layer plasma during plasma discharges, where it quickly liquefies and turns into an aerosol. The use of this 'lithium dropper' is under study at the Experimental Advanced Superconducting Tokamak (EAST), where the potential benefits of real-time wall conditioning via lithium injection are being tested. Here, we present an analysis of the recycling characteristics during EAST experiments testing active lithium injection in order to assess recycling reduction and control. Lithium aerosol was injected from the top of the machine, with one system dropping lithium near the X-point and another into the low-field side divertor leg. The injection of lithium into the SOL reduced divertor recycling, as evidenced by reduced Dα emission with ion flux measured by probes relatively unchanged. This effect is strongest in the active divertor, confirming the lithium is transported to strongly plasma-wetted areas. Quantitative analysis of the recycling changes using the SOLPS edge plasma and neutral transport code indicated a 20% reduction in recycling coefficient with lithium injection.
KW - Divertor
KW - Experimental Advanced Superconducting Tokamak (EAST)
KW - lithium wall coatings
UR - https://www.scopus.com/pages/publications/85041683497
UR - https://www.scopus.com/inward/citedby.url?scp=85041683497&partnerID=8YFLogxK
U2 - 10.1109/TPS.2017.2789119
DO - 10.1109/TPS.2017.2789119
M3 - Article
AN - SCOPUS:85041683497
SN - 0093-3813
VL - 46
SP - 1081
EP - 1085
JO - IEEE Transactions on Plasma Science
JF - IEEE Transactions on Plasma Science
IS - 5
ER -