Optimizing the Super H-mode pedestal to improve performance and facilitate divertor integration

M. Knolker; P. B. Snyder; T. E. Evans; T. Wilks; D. Eldon; B. Grierson; Aaro Järvinen; X. Jian; F. Laggner; J. McClenaghan; A. G. McLean; T. Osborne; C. Paz-Soldan; F. Scotti; W. Solomon

doi:10.1063/5.0011008

Optimizing the Super H-mode pedestal to improve performance and facilitate divertor integration

M. Knolker^*
, P. B. Snyder
, T. E. Evans
, T. Wilks
, D. Eldon
, B. Grierson
, Aaro Järvinen
, X. Jian
, F. Laggner
, J. McClenaghan
, A. G. McLean
, T. Osborne
, C. Paz-Soldan
, F. Scotti
, W. Solomon

^*Corresponding author for this work

Not published at VTT

Oak Ridge National Laboratory (ORNL)
General Atomics
MIT Massachusetts Institute of Technology
Princeton University
Lawrence Livermore National Laboratory
University of California, San Diego

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

14 Citations (Scopus)

Abstract

Access to Super H-mode is demonstrated for moderately shaped plasmas in agreement with EPED [Snyder et al., Phys. Plasmas 16, 056118 (2009)] predictions. In particular, Super H-mode is realized in a DIII-D shape that is accessible to the JET tokamak. The reduced triangularity of the JET-compatible shape compared to previous Super H-mode plasma shapes does not prevent deep ascension into the so-called Super H-mode "channel."Operationally, access is enabled and optimized by delaying the neutral beam power injection and, thus, protracting the L-H transition. In highly shaped DIII-D plasmas, the injection of nitrogen sufficient for the establishment of a radiative divertor is shown to be possible during Super H-mode without pedestal degradation. Due to its increased stored energy and radiative divertor integration capabilities, Super H-mode is a promising candidate as operating regime for JET, ITER, and future fusion reactors.

Original language	English
Article number	102506
Journal	Physics of Plasmas
Volume	27
Issue number	10
DOIs	https://doi.org/10.1063/5.0011008
Publication status	Published - Oct 2020
MoE publication type	A1 Journal article-refereed

Funding

This research was supported by the General Atomics Postgraduate Research Participation Program administered by ORAU. This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Award Nos. DE-FC02–04ER54698, DE-AC02–09CH11466, DE-AC52–07NA27344, DE-SC0018030, and DE-SC0018287.

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This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

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10.1063/5.0011008

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Knolker, M., Snyder, P. B., Evans, T. E., Wilks, T., Eldon, D., Grierson, B., Järvinen, A., Jian, X., Laggner, F., McClenaghan, J., McLean, A. G., Osborne, T., Paz-Soldan, C., Scotti, F., & Solomon, W. (2020). Optimizing the Super H-mode pedestal to improve performance and facilitate divertor integration. Physics of Plasmas, 27(10), Article 102506. https://doi.org/10.1063/5.0011008

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title = "Optimizing the Super H-mode pedestal to improve performance and facilitate divertor integration",

abstract = "Access to Super H-mode is demonstrated for moderately shaped plasmas in agreement with EPED [Snyder et al., Phys. Plasmas 16, 056118 (2009)] predictions. In particular, Super H-mode is realized in a DIII-D shape that is accessible to the JET tokamak. The reduced triangularity of the JET-compatible shape compared to previous Super H-mode plasma shapes does not prevent deep ascension into the so-called Super H-mode {"}channel.{"}Operationally, access is enabled and optimized by delaying the neutral beam power injection and, thus, protracting the L-H transition. In highly shaped DIII-D plasmas, the injection of nitrogen sufficient for the establishment of a radiative divertor is shown to be possible during Super H-mode without pedestal degradation. Due to its increased stored energy and radiative divertor integration capabilities, Super H-mode is a promising candidate as operating regime for JET, ITER, and future fusion reactors.",

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AU - Knolker, M.

AU - Snyder, P. B.

AU - Evans, T. E.

AU - Wilks, T.

AU - Eldon, D.

AU - Grierson, B.

AU - Järvinen, Aaro

AU - Jian, X.

AU - Laggner, F.

AU - McClenaghan, J.

AU - McLean, A. G.

AU - Osborne, T.

AU - Paz-Soldan, C.

AU - Scotti, F.

AU - Solomon, W.

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N2 - Access to Super H-mode is demonstrated for moderately shaped plasmas in agreement with EPED [Snyder et al., Phys. Plasmas 16, 056118 (2009)] predictions. In particular, Super H-mode is realized in a DIII-D shape that is accessible to the JET tokamak. The reduced triangularity of the JET-compatible shape compared to previous Super H-mode plasma shapes does not prevent deep ascension into the so-called Super H-mode "channel."Operationally, access is enabled and optimized by delaying the neutral beam power injection and, thus, protracting the L-H transition. In highly shaped DIII-D plasmas, the injection of nitrogen sufficient for the establishment of a radiative divertor is shown to be possible during Super H-mode without pedestal degradation. Due to its increased stored energy and radiative divertor integration capabilities, Super H-mode is a promising candidate as operating regime for JET, ITER, and future fusion reactors.

AB - Access to Super H-mode is demonstrated for moderately shaped plasmas in agreement with EPED [Snyder et al., Phys. Plasmas 16, 056118 (2009)] predictions. In particular, Super H-mode is realized in a DIII-D shape that is accessible to the JET tokamak. The reduced triangularity of the JET-compatible shape compared to previous Super H-mode plasma shapes does not prevent deep ascension into the so-called Super H-mode "channel."Operationally, access is enabled and optimized by delaying the neutral beam power injection and, thus, protracting the L-H transition. In highly shaped DIII-D plasmas, the injection of nitrogen sufficient for the establishment of a radiative divertor is shown to be possible during Super H-mode without pedestal degradation. Due to its increased stored energy and radiative divertor integration capabilities, Super H-mode is a promising candidate as operating regime for JET, ITER, and future fusion reactors.

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ER -

Optimizing the Super H-mode pedestal to improve performance and facilitate divertor integration

Abstract

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