TCV heating and divertor upgrades. (12th November 2019)

• Record Type: Journal Article
• Authors: Fasoli, A.; Reimerdes, H.; Alberti, S.; Baquero-Ruiz, M.; Duval, B.P.; Havlikova, E.; Karpushov, A.; Moret, J.-M.; Toussaint, M.; Elaian, H.; Silva, M.; Theiler, C.; Vaccaro, D.
• Other Names: collab.
• Is Part Of: Nuclear fusion. Volume 60:Number 1(2020)
• Publication Date: 2019-11-12
• Subjects: TCV tokamak -- divertor -- ECRH -- NBH -- diagnostics; Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/ab4c56
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: The operational range and the reactor relevance of the TCV experiments are being enhanced by two sets of major upgrades. The first includes the installation of neutral beam injection (NBI) and new electron cyclotron (EC) auxiliary heating sources, to reach ITER relevant beta values and vary the electron to ion temperature ratio. A 15–30 keV, 1 MW tangential NBI system has been operational on TCV since 2015. A second beam of 1 MW, 50–60 keV ion energy, also aligned tangentially but opposite to the first beam, is foreseen to approach beta limits, vary the applied torque through zero and probe suprathermal ion physics. For the EC power, two 0.75 MW gyrotrons at the second harmonic have been installed. The next step will add two 1 MW dual frequency gyrotrons, one of which is currently being commissioned. These heating upgrades will increase the total available power for high-density plasmas from 1.25 MW to 5.0 MW. The rest of the upgrade consists of installing an in-vessel structure to form a divertor chamber of increased closure, to reach higher neutral divertor densities and impurity compression and thereby extend TCV divertor regimes toward more reactor relevant conditions for conventional and advanced divertor configurations. Graphite gas baffles will be installed inside the TCV vessel to delineate divertor and main chamber regions. The first set of baffles features 32 tiles on the high and 64 tiles on the low-field side, with geometry guided by simulations performed using the SOLPS-ITER code. The baffles are expected to be effective for a wide range of divertor configurations, including snowflake and super-X divertors, yet maintain plasma close to the inner wall for improved passive stabilization. The baffle dimensions may be varied in the future to modify the divertor closure. Control of the plasma, neutral and impurity densities will be achieved by a combination of toroidally distributed gas injection valves and impurity seeding, and a possible addition of cryo-condensation pumps. Significant diagnostic developments will be undertaken, to better characterize the divertor plasma, measure power and particle deposition at the strike points, and, specifically, improve our physics understanding of the detachment process.