Initial TCV operation with a baffled divertor

Reimerdes, Holger; Duval, B. P.; Elaian, H.; Fasoli, Ambrogio; Février, Olivier; Theiler, Christian; Bagnato, F.; Baquero-Ruiz, M.; Blanchard, P.; Brida, D.; Colandrea, C.; De Oliveira, H.; Galassi, Davide; Gorno, Sophie; Henderson, Stuart; Komm, Michael; Linehan, B.; Martinelli, L.; Maurizio, R.; Moret, J. -M.; Perek, A.; Raj, H.; Sheikh, Umar; Testa, Duccio; Toussaint, M.; Tsui, Cedric K.; Wensing, Mirko

doi:10.1088/1741-4326/abd196

Initial TCV operation with a baffled divertor

Journal Article · Sun Jan 10 23:00:00 EST 2021 · Nuclear Fusion

DOI:https://doi.org/10.1088/1741-4326/abd196· OSTI ID:1851397

^[1]; Duval, B. P. ^[2]; Elaian, H. ^[2]; ^[2]; ^[2]; ^[2]; Bagnato, F. ^[2]; Baquero-Ruiz, M. ^[2]; Blanchard, P. ^[2]; Brida, D. ^[3]; Colandrea, C. ^[2]; De Oliveira, H. ^[2]; ^[2]; ^[2]; ^[4]; ^[5]; Linehan, B. ^[6]; Martinelli, L. ^[2]; Maurizio, R. ^[2]; Moret, J. -M. ^[2] more »

Ecole Polytechnique Federale Lausanne (EPFL) (Switzerland); OSTI
Ecole Polytechnique Federale Lausanne (EPFL) (Switzerland)
Max Planck Institute for Plasma Physics, Garching (Germany)
UK Atomic Energy Authority (UKAEA), Abingdon (United Kingdom). Culham Science Centre
Czech Academy of Sciences (CAS), Prague (Czech Republic). Institute of Plasma Physics
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Dutch Institute for Fundamental Energy Research, Eindhoven (Netherlands)
Univ. of California, San Diego, La Jolla, CA (United States)

The Tokamak à Configuration Variable (TCV) tokamak is in the midst of an upgrade to further its capability to investigate conventional and alternative divertor configurations. To that end, modular and removable gas baffles have been installed to decrease the coupling between the divertor and the plasma core. The baffles primarily seek to suppress the transit of recycling neutrals to closed flux surfaces. A first experimental campaign with the gas baffles has shown that the baffled divertor remains compatible with a wide range of configurations including snowflake and super-X divertors. Plasma density ramp experiments reveal an increase of the neutral pressure in the divertor by up to a factor ×5 compared to the unbaffled divertor and thereby qualitatively confirm simulations with the SOLPS-ITER code that were used to guide the baffle design. Finally, together with a range of new and upgraded divertor diagnostics, the baffled TCV divertor is now used to validate divertor models for ITER and next step devices with particular emphasis on geometric variations.

View Accepted Manuscript (DOE)

Research Organization:: Univ. of California, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC); Swiss National Science Foundation

Contributing Organization:: TCV Team; EUROfusion MST1 Team

Grant/Contract Number:: SC0010529

OSTI ID:: 1851397

Alternate ID(s):: OSTI ID: 23129588

Journal Information:: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 2 Vol. 61; ISSN 0029-5515

Publisher:: IOP ScienceCopyright Statement

Country of Publication:: United States

Language:: English

References (15)

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