TCV experiments towards the development of a plasma exhaust solution

H  Reimerdes; B. P. Duval; J. R. Harrison; B. Labit; B. Lipschultz; T. Lunt; C. Theiler; C. K. Tsui; K. Verhaegh; W. A.J. Vijvers; J A Boedo; G  Calabro; F  Crisanti; P  Innocente; Roberto  Maurizio; V  Pericoli; U. A. Sheikh; M. Spolare; N. Vianello

doi:10.1088/1741-4326/aa82c2

TCV experiments towards the development of a plasma exhaust solution

H Reimerdes, B. P. Duval, J. R. Harrison, B. Labit, B. Lipschultz, T. Lunt, C. Theiler, C. K. Tsui, K. Verhaegh, W. A.J. Vijvers, J A Boedo, G Calabro, F Crisanti, P Innocente, Roberto Maurizio, V Pericoli, U. A. Sheikh, M. Spolare, N. Vianello

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

Abstract

Research towards a plasma exhaust solution for a fusion power plant aims at validating edge physics models, strengthening predictive capabilities and improving the divertor configuration. The TCV tokamak is extensively used to investigate the extent that geometric configuration modifications can affect plasma exhaust performance. Recent TCV experiments continue previous detachment studies of Ohmically heated L-mode plasmas in standard single-null configurations, benefitting from a range of improved diagnostic capabilities. Studies were extended to nitrogen seeding and an entire suite of alternative magnetic configurations, including flux flaring towards the target (X divertor), increasing the outer target radius (Super-X) and movement of a secondary x-point inside the vessel (X-point target) as well as the entire range of snowflake configurations. Nitrogen seeding into a snowflake minus configuration demonstrated a regime with strong radiation in the large region between the two x-points, confirming EMC3-Eirene simulations, and opening a promising path towards highly radiating regimes with limited adverse effects on core performance.

Original language	English
Article number	126007
Number of pages	9
Journal	Nuclear Fusion
Volume	57
Issue number	12
DOIs	https://doi.org/10.1088/1741-4326/aa82c2
Publication status	Published - 12 Sept 2017

Bibliographical note

© 2017 Ecole Polytechnique Federale de Lausanne. This is an author-produced version of a paper accepted for publication. Uploaded with permission of the publisher/copyright holder. Further copying may not be permitted; contact the publisher for details

Keywords

alternative divertor configurations
detachment
divertor physics
tokamak power exhaust

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Reimerdes, H., Duval, B. P., Harrison, J. R., Labit, B., Lipschultz, B., Lunt, T., Theiler, C., Tsui, C. K., Verhaegh, K., Vijvers, W. A. J., Boedo, J. A., Calabro, G., Crisanti, F., Innocente, P., Maurizio, R., Pericoli, V., Sheikh, U. A., Spolare, M., & Vianello, N. (2017). TCV experiments towards the development of a plasma exhaust solution. Nuclear Fusion, 57(12), Article 126007. https://doi.org/10.1088/1741-4326/aa82c2

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abstract = "Research towards a plasma exhaust solution for a fusion power plant aims at validating edge physics models, strengthening predictive capabilities and improving the divertor configuration. The TCV tokamak is extensively used to investigate the extent that geometric configuration modifications can affect plasma exhaust performance. Recent TCV experiments continue previous detachment studies of Ohmically heated L-mode plasmas in standard single-null configurations, benefitting from a range of improved diagnostic capabilities. Studies were extended to nitrogen seeding and an entire suite of alternative magnetic configurations, including flux flaring towards the target (X divertor), increasing the outer target radius (Super-X) and movement of a secondary x-point inside the vessel (X-point target) as well as the entire range of snowflake configurations. Nitrogen seeding into a snowflake minus configuration demonstrated a regime with strong radiation in the large region between the two x-points, confirming EMC3-Eirene simulations, and opening a promising path towards highly radiating regimes with limited adverse effects on core performance.",

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Reimerdes, H, Duval, BP, Harrison, JR, Labit, B, Lipschultz, B, Lunt, T, Theiler, C, Tsui, CK, Verhaegh, K , Vijvers, WAJ, Boedo, JA, Calabro, G, Crisanti, F, Innocente, P, Maurizio, R, Pericoli, V, Sheikh, UA, Spolare, M & Vianello, N 2017, 'TCV experiments towards the development of a plasma exhaust solution', Nuclear Fusion, vol. 57, no. 12, 126007. https://doi.org/10.1088/1741-4326/aa82c2

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AU - Duval, B. P.

AU - Harrison, J. R.

AU - Labit, B.

AU - Lipschultz, B.

AU - Lunt, T.

AU - Theiler, C.

AU - Tsui, C. K.

AU - Verhaegh, K.

AU - Vijvers, W. A.J.

AU - Boedo, J A

AU - Calabro, G

AU - Crisanti, F

AU - Innocente, P

AU - Maurizio, Roberto

AU - Pericoli, V

AU - Sheikh, U. A.

AU - Spolare, M.

AU - Vianello, N.

N1 - © 2017 Ecole Polytechnique Federale de Lausanne. This is an author-produced version of a paper accepted for publication. Uploaded with permission of the publisher/copyright holder. Further copying may not be permitted; contact the publisher for details

PY - 2017/9/12

Y1 - 2017/9/12

N2 - Research towards a plasma exhaust solution for a fusion power plant aims at validating edge physics models, strengthening predictive capabilities and improving the divertor configuration. The TCV tokamak is extensively used to investigate the extent that geometric configuration modifications can affect plasma exhaust performance. Recent TCV experiments continue previous detachment studies of Ohmically heated L-mode plasmas in standard single-null configurations, benefitting from a range of improved diagnostic capabilities. Studies were extended to nitrogen seeding and an entire suite of alternative magnetic configurations, including flux flaring towards the target (X divertor), increasing the outer target radius (Super-X) and movement of a secondary x-point inside the vessel (X-point target) as well as the entire range of snowflake configurations. Nitrogen seeding into a snowflake minus configuration demonstrated a regime with strong radiation in the large region between the two x-points, confirming EMC3-Eirene simulations, and opening a promising path towards highly radiating regimes with limited adverse effects on core performance.

AB - Research towards a plasma exhaust solution for a fusion power plant aims at validating edge physics models, strengthening predictive capabilities and improving the divertor configuration. The TCV tokamak is extensively used to investigate the extent that geometric configuration modifications can affect plasma exhaust performance. Recent TCV experiments continue previous detachment studies of Ohmically heated L-mode plasmas in standard single-null configurations, benefitting from a range of improved diagnostic capabilities. Studies were extended to nitrogen seeding and an entire suite of alternative magnetic configurations, including flux flaring towards the target (X divertor), increasing the outer target radius (Super-X) and movement of a secondary x-point inside the vessel (X-point target) as well as the entire range of snowflake configurations. Nitrogen seeding into a snowflake minus configuration demonstrated a regime with strong radiation in the large region between the two x-points, confirming EMC3-Eirene simulations, and opening a promising path towards highly radiating regimes with limited adverse effects on core performance.

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KW - divertor physics

KW - tokamak power exhaust

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DO - 10.1088/1741-4326/aa82c2

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SN - 0029-5515

VL - 57

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 12

M1 - 126007

ER -

TCV experiments towards the development of a plasma exhaust solution

Abstract

Bibliographical note

Keywords

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