Abstract
ICRH was extensively used in the 2015-16 JET-ILW (ITER like wall) experimental campaign; bulk heating together with high-Z impurity chase-out from plasma centre importantly contributed to the good DD fusion performance obtained recently in JET. Power up to 6 MW was launched in H-mode deuterium plasmas and 8 MW during the hydrogen campaign. The ILA was re-installed and contributed positively to the availability of ICRH power. The ILA produces slightly less high-Z impurities than the A2's and the PWI measured via Be line emission on limiters is in the same ballpark. Specific experiments were conducted to optimise ICRH scenarios in preparation for DT in particular the dual frequency scheme, (H)D and (He)D were tested. In addition, it was confirmed that the (D)H scenario is accessible in a ILW environment and the novel 3-ions ICRH scheme was validated experimentally.
Original language | English |
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Article number | 02004 |
Journal | EPJ Web of Conferences |
Volume | 157 |
DOIs | |
State | Published - Oct 23 2017 |
Externally published | Yes |
Event | 22nd Topical Conference on Radio-Frequency Power in Plasmas 2017 - Aix en Provence, France Duration: May 30 2017 → Jun 2 2017 |
Funding
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 20142018 under grant agreement No 633053 and from the RCUK Energy Programme [grant number EP/P012450/1]. The views and opinions expressed herein do not necessarily reflect those of the European Commission 'To obtain further information on the data and models underlying this paper please contact [email protected].
Funders | Funder number |
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RCUK Energy Programme | EP/P012450/1 |
Horizon 2020 Framework Programme | |
H2020 Euratom | 633053 |
H2020 Euratom |