Initial TCV operation with a baffled divertor

TCV team; EUROfusion MST1 Team

doi:10.1088/1741-4326/abd196

Initial TCV operation with a baffled divertor

TCV team, EUROfusion MST1 Team

Science and Technology of Nuclear Fusion

Research output: Contribution to journal › Article › Academic › peer-review

37 Citations (Scopus)

Abstract

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. 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.

Original language	English
Article number	024002
Journal	Nuclear Fusion
Volume	61
Issue number	2
DOIs	https://doi.org/10.1088/1741-4326/abd196
Publication status	Published - Feb 2021

Bibliographical note

Funding Information:
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014–2018 and 2019–2020 under Grant Agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work was supported in part by the Swiss National Science Foundation and the US Department of Energy under Award Number DE-SC0010529.

Funding

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014–2018 and 2019–2020 under Grant Agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work was supported in part by the Swiss National Science Foundation and the US Department of Energy under Award Number DE-SC0010529.

Funders	Funder number
U.S. Department of Energy	DE-SC0010529
European Union's Horizon 2020 - Research and Innovation Framework Programme	633053
European Union's Horizon 2020 - Research and Innovation Framework Programme
Schweizerischer Nationalfonds zur Förderung der Wissenschaftlichen Forschung

Keywords

Divertor
Plasma exhaust
TCV tokamak

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10.1088/1741-4326/abd196

Cite this

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title = "Initial TCV operation with a baffled divertor",

abstract = "The Tokamak {\`a} 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. 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.",

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note = "Funding Information: This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014–2018 and 2019–2020 under Grant Agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. This work was supported in part by the Swiss National Science Foundation and the US Department of Energy under Award Number DE-SC0010529. ",

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AU - Theiler, C.

AU - Bagnato, F.

AU - Baquero-Ruiz, M.

AU - Blanchard, P.

AU - Brida, D.

AU - Colandrea, C.

AU - de Oliveira, H.

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AU - Gorno, S.

AU - Henderson, S.

AU - Komm, M.

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AU - Martinelli, L.

AU - Maurizio, R.

AU - Moret, J. M.

AU - Perek, A.

AU - Raj, H.

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AU - Testa, D.

AU - Toussaint, M.

AU - Tsui, C. K.

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AB - 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. 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.

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JO - Nuclear Fusion

JF - Nuclear Fusion

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ER -

Initial TCV operation with a baffled divertor

Abstract

Bibliographical note

Funding

Keywords

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