Status, scientific results and technical improvements of the NBH on TCV tokamak

The TCV tokamak contributes to physics understanding in fusion reactor research by a wide set of experimental tools, like flexible shaping and high power ECRH. A 1MW, 25 keV deuterium heating neutral beam (NB) has been installed in 2015 and it was operated from 2016 in SPC-TCV domestic and EUROfusion MST1 experimental campaigns ((similar to)50/50%). The rate of failures of the beam is less than 5%. Ion temperatures up to 3.5 keV have been achieved in ELMy H-mode, with a good agreement with ASTRA predictive simulations. The NB enables TCV to access ITER-like beta(N) values (1.8) and T-e/T-i (similar to)1, allowing investigations of innovative plasma features in ITER relevant ELMy H-mode. The advanced Tokamak route was also pursued, with stationary, fully non-inductive discharges sustained by ECCD and NBCD reaching beta(similar to)(N)1.4-1.7. Real-time control of the NB power has been implemented in 2018 and presented together with the statistics of NB operation on the TCV. During commissioning, the NB showed unacceptable heating of the TCV beam duct, indicating a higher power deposition than expected on duct walls. A high beam divergence has been found by dedicated measurement of 3-D beam power density distribution with an expressly designed device (IR measurement on tungsten target).


Published in:
Fusion Engineering And Design, 146, 773-777
Presented at:
30th Symposium on Fusion Technology (SOFT), Messina, ITALY, Sep 16-21, 2018
Year:
Sep 01 2019
ISSN:
0920-3796
1873-7196
Keywords:
Laboratories:


Note: The status of this file is: Anyone


 Record created 2019-10-23, last modified 2020-04-20

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