Abstract
| Original language | English |
|---|---|
| Article number | 095003 |
| Journal | Nuclear Fusion |
| Volume | 58 |
| Issue number | 9 |
| DOIs | |
| Publication status | Published - 20 Jul 2018 |
| MoE publication type | A2 Review article in a scientific journal |
Funding
This work is supported by the National Magnetic Confinement Fusion Science Program of China (Grant No. 2015GB102003, 2013GB106001B, 2013GB112003, 2015GB101002), the National Natural Science Foundation of China (Grant No. 11675214, 11175206, 11305211 and 11275233), the National Key R&D Program of China (Grant No. 2016YFA0400600, and 2016YFA0400602), Hefei Science Center CAS (2016HSC-IU008), the JSPS-NRF-NSFC A3 Foresight Program in the field of Plasma Physics (NSFC No. 11261140328), and K C Wong Education Foundation. Part of the work was conducted on the Alcator C-Mod tokamak, a DoE Office of Science user facility, and is supported by USDoE awards DE-FC02-99ER54512, DE-AC02-09CH11466, and DoE Grant DE-SC0010492. It is partly supported by the China-Italy and the China-France Collaboration program. We also give thanks to the support from the IOS TG of the ITPA. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. Work has been part-funded by the RCUK Energy Programme (grant number EP/P012450/1).
Keywords
- ITER
- lower hybrid current drive
- magnetic fusion