Upgrade of the TCV tokamak, first phase: Neutral beam heating system

Experiments on TCV are designed to complement the work at large integrated tokamak facilities (such as JET) to provide a stepwise approach to extrapolation to ITER and DEMO in areas where medium-size tokamaks can often exploit their experimental capabilities and flexibility. Improving the understanding and control requirements of burning plasmas is a major scientific challenge, requiring access to plasma regimes and configurations with high normalized plasma pressure and a wide range of ion to electron temperature ratios, including T-e/T-i similar to 1. These conditions will be explored by adding a 1 MW neutral heating beam to TCV's auxiliary for direct ion heating (2015) and increasing the ECH power injected in X-mode at the third harmonic (2 MW in 2015-2016). The manufacturing of the neutral beam injector was launched in 2014. (C) 2015 Elsevier B.V. All rights reserved.


Published in:
Fusion Engineering And Design, 96-97, 493-497
Presented at:
28th Symposium on Fusion Technology (SOFT), San Sebastian, SPAIN, SEP 29-OCT 03, 2014
Year:
2015
Publisher:
Lausanne, Elsevier Science Sa
ISSN:
0920-3796
Keywords:
Laboratories:




 Record created 2016-02-16, last modified 2018-01-28


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