Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution.

V. A. Soukhanovskii; S. L. Allen; M. E. Fenstermacher; C. J. Lasnier; M. A. Makowski; A. G. McLean; E. T. Meier; W. H. Meyer; T. D. Rognlien; D. D. Ryutov; F. Scotti; E. Kolemen; R. E. Bell; A. Diallo; S. Gerhardt; R. Kaita; S. Kaye; B. P. Leblanc; R. Maingi; M. Podesta; A. L. Roquemore; R. J. Groebner; A. W. Hyatt; A. W. Leonard; T. H. Osborne; T. W. Petrie; J. W. Ahn; R. Raman; J. G. Watkins

doi:10.1109/SOFE.2015.7482263

Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution.

V. A. Soukhanovskii
, S. L. Allen
, M. E. Fenstermacher
, C. J. Lasnier
, M. A. Makowski
, A. G. McLean
, E. T. Meier
, W. H. Meyer
, T. D. Rognlien
, D. D. Ryutov
, F. Scotti
, E. Kolemen
, R. E. Bell
, A. Diallo
, S. Gerhardt
, R. Kaita
, S. Kaye
, B. P. Leblanc
, R. Maingi
, M. Podesta

A. L. Roquemore, R. J. Groebner, A. W. Hyatt, A. W. Leonard, T. H. Osborne, T. W. Petrie, J. W. Ahn, R. Raman, J. G. Watkins

Princeton University

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Abstract

Experimental results from the National Spherical Torus Experiment (NSTX), a medium-size spherical tokamak with a compact divertor, and DIII-D, a large conventional aspect ratio tokamak, demonstrate that the snowflake (SF) divertor configuration (D.D. Ryutov, Phys. Plasmas, 14, 064502, 2007) may provide a promising solution for mitigating divertor heat loads and target plate erosion compatible with core H-mode confinement in future fusion devices, where the standard radiative divertor solution may be inadequate. In NSTX, where the initial high-power SF experiment were performed, the SF divertor was compatible with H-mode confinement, and led to the destabilization of large ELMs. However, a stable partial detachment of the outer strike point was also achieved where inter-ELM peak heat flux was reduced by factors 3-5, and peak ELM heat flux was reduced by up to 80% (cf. standard divertor). The DIII-D studies show the SF divertor enables significant power spreading in attached and radiative divertor conditions. Results include: compatibility with the core and pedestal, peak inter-ELM divertor heat flux reduction due to geometry at lower ne, and ELM energy and divertor peak heat flux reduction, especially prominent in radiative D2-seeded SF divertor, and nearly complete power detachment and broader radiated power distribution in the radiative D2-seeded SF divertor at PSOL = 3-4 MW. A variety of SF configurations can be supported by the divertor coil set in NSTX Upgrade. Edge transport modeling with the multi-fluid edge transport code UEDGE shows that the radiative SF divertor can successfully reduce peak divertor heat flux for the projected PSOL ≃ 9 MW case. The radiative SF divertor with carbon impurity provides a wider ne operating window, 50% less argon is needed in the impurity-seeded SF configuration to achieve similar qpeak reduction factors (cf. standard divertor).

Original language	American English
Title of host publication	2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015
Publisher	Institute of Electrical and Electronics Engineers Inc.
ISBN (Electronic)	9781479982646
DOIs	https://doi.org/10.1109/SOFE.2015.7482263
State	Published - May 31 2016
Event	26th IEEE Symposium on Fusion Engineering, SOFE 2015 - Austin, United States Duration: May 31 2015 → Jun 4 2015

Publication series

Name	Proceedings - Symposium on Fusion Engineering
Volume	2016-May

Other

Other	26th IEEE Symposium on Fusion Engineering, SOFE 2015
Country/Territory	United States
City	Austin
Period	5/31/15 → 6/4/15

ASJC Scopus subject areas

Nuclear and High Energy Physics
Nuclear Energy and Engineering

Access to Document

10.1109/SOFE.2015.7482263

Cite this

Soukhanovskii, V. A., Allen, S. L., Fenstermacher, M. E., Lasnier, C. J., Makowski, M. A., McLean, A. G., Meier, E. T., Meyer, W. H., Rognlien, T. D., Ryutov, D. D., Scotti, F., Kolemen, E., Bell, R. E., Diallo, A., Gerhardt, S., Kaita, R., Kaye, S., Leblanc, B. P., Maingi, R., ... Watkins, J. G. (2016). Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution. In 2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015 Article 7482263 (Proceedings - Symposium on Fusion Engineering; Vol. 2016-May). Institute of Electrical and Electronics Engineers Inc.. https://doi.org/10.1109/SOFE.2015.7482263

@inproceedings{55a874927ddc4cbd91934d325bdf4308,

title = "Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution.",

abstract = "Experimental results from the National Spherical Torus Experiment (NSTX), a medium-size spherical tokamak with a compact divertor, and DIII-D, a large conventional aspect ratio tokamak, demonstrate that the snowflake (SF) divertor configuration (D.D. Ryutov, Phys. Plasmas, 14, 064502, 2007) may provide a promising solution for mitigating divertor heat loads and target plate erosion compatible with core H-mode confinement in future fusion devices, where the standard radiative divertor solution may be inadequate. In NSTX, where the initial high-power SF experiment were performed, the SF divertor was compatible with H-mode confinement, and led to the destabilization of large ELMs. However, a stable partial detachment of the outer strike point was also achieved where inter-ELM peak heat flux was reduced by factors 3-5, and peak ELM heat flux was reduced by up to 80\% (cf. standard divertor). The DIII-D studies show the SF divertor enables significant power spreading in attached and radiative divertor conditions. Results include: compatibility with the core and pedestal, peak inter-ELM divertor heat flux reduction due to geometry at lower ne, and ELM energy and divertor peak heat flux reduction, especially prominent in radiative D2-seeded SF divertor, and nearly complete power detachment and broader radiated power distribution in the radiative D2-seeded SF divertor at PSOL = 3-4 MW. A variety of SF configurations can be supported by the divertor coil set in NSTX Upgrade. Edge transport modeling with the multi-fluid edge transport code UEDGE shows that the radiative SF divertor can successfully reduce peak divertor heat flux for the projected PSOL ≃ 9 MW case. The radiative SF divertor with carbon impurity provides a wider ne operating window, 50\% less argon is needed in the impurity-seeded SF configuration to achieve similar qpeak reduction factors (cf. standard divertor).",

author = "Soukhanovskii, \{V. A.\} and Allen, \{S. L.\} and Fenstermacher, \{M. E.\} and Lasnier, \{C. J.\} and Makowski, \{M. A.\} and McLean, \{A. G.\} and Meier, \{E. T.\} and Meyer, \{W. H.\} and Rognlien, \{T. D.\} and Ryutov, \{D. D.\} and F. Scotti and E. Kolemen and Bell, \{R. E.\} and A. Diallo and S. Gerhardt and R. Kaita and S. Kaye and Leblanc, \{B. P.\} and R. Maingi and M. Podesta and Roquemore, \{A. L.\} and Groebner, \{R. J.\} and Hyatt, \{A. W.\} and Leonard, \{A. W.\} and Osborne, \{T. H.\} and Petrie, \{T. W.\} and Ahn, \{J. W.\} and R. Raman and Watkins, \{J. G.\}",

note = "Publisher Copyright: {\textcopyright} 2015 IEEE.; 26th IEEE Symposium on Fusion Engineering, SOFE 2015 ; Conference date: 31-05-2015 Through 04-06-2015",

year = "2016",

month = may,

day = "31",

doi = "10.1109/SOFE.2015.7482263",

language = "American English",

series = "Proceedings - Symposium on Fusion Engineering",

publisher = "Institute of Electrical and Electronics Engineers Inc.",

booktitle = "2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015",

address = "United States",

}

Soukhanovskii, VA, Allen, SL, Fenstermacher, ME, Lasnier, CJ, Makowski, MA, McLean, AG, Meier, ET, Meyer, WH, Rognlien, TD, Ryutov, DD, Scotti, F, Kolemen, E, Bell, RE, Diallo, A , Gerhardt, S, Kaita, R, Kaye, S , Leblanc, BP , Maingi, R, Podesta, M, Roquemore, AL, Groebner, RJ, Hyatt, AW, Leonard, AW, Osborne, TH, Petrie, TW, Ahn, JW, Raman, R & Watkins, JG 2016, Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution. in 2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015., 7482263, Proceedings - Symposium on Fusion Engineering, vol. 2016-May, Institute of Electrical and Electronics Engineers Inc., 26th IEEE Symposium on Fusion Engineering, SOFE 2015, Austin, United States, 5/31/15. https://doi.org/10.1109/SOFE.2015.7482263

Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution. / Soukhanovskii, V. A.; Allen, S. L.; Fenstermacher, M. E. et al.
2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015. Institute of Electrical and Electronics Engineers Inc., 2016. 7482263 (Proceedings - Symposium on Fusion Engineering; Vol. 2016-May).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

TY - GEN

T1 - Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution.

AU - Soukhanovskii, V. A.

AU - Allen, S. L.

AU - Fenstermacher, M. E.

AU - Lasnier, C. J.

AU - Makowski, M. A.

AU - McLean, A. G.

AU - Meier, E. T.

AU - Meyer, W. H.

AU - Rognlien, T. D.

AU - Ryutov, D. D.

AU - Scotti, F.

AU - Kolemen, E.

AU - Bell, R. E.

AU - Diallo, A.

AU - Gerhardt, S.

AU - Kaita, R.

AU - Kaye, S.

AU - Leblanc, B. P.

AU - Maingi, R.

AU - Podesta, M.

AU - Roquemore, A. L.

AU - Groebner, R. J.

AU - Hyatt, A. W.

AU - Leonard, A. W.

AU - Osborne, T. H.

AU - Petrie, T. W.

AU - Ahn, J. W.

AU - Raman, R.

AU - Watkins, J. G.

PY - 2016/5/31

Y1 - 2016/5/31

N2 - Experimental results from the National Spherical Torus Experiment (NSTX), a medium-size spherical tokamak with a compact divertor, and DIII-D, a large conventional aspect ratio tokamak, demonstrate that the snowflake (SF) divertor configuration (D.D. Ryutov, Phys. Plasmas, 14, 064502, 2007) may provide a promising solution for mitigating divertor heat loads and target plate erosion compatible with core H-mode confinement in future fusion devices, where the standard radiative divertor solution may be inadequate. In NSTX, where the initial high-power SF experiment were performed, the SF divertor was compatible with H-mode confinement, and led to the destabilization of large ELMs. However, a stable partial detachment of the outer strike point was also achieved where inter-ELM peak heat flux was reduced by factors 3-5, and peak ELM heat flux was reduced by up to 80% (cf. standard divertor). The DIII-D studies show the SF divertor enables significant power spreading in attached and radiative divertor conditions. Results include: compatibility with the core and pedestal, peak inter-ELM divertor heat flux reduction due to geometry at lower ne, and ELM energy and divertor peak heat flux reduction, especially prominent in radiative D2-seeded SF divertor, and nearly complete power detachment and broader radiated power distribution in the radiative D2-seeded SF divertor at PSOL = 3-4 MW. A variety of SF configurations can be supported by the divertor coil set in NSTX Upgrade. Edge transport modeling with the multi-fluid edge transport code UEDGE shows that the radiative SF divertor can successfully reduce peak divertor heat flux for the projected PSOL ≃ 9 MW case. The radiative SF divertor with carbon impurity provides a wider ne operating window, 50% less argon is needed in the impurity-seeded SF configuration to achieve similar qpeak reduction factors (cf. standard divertor).

AB - Experimental results from the National Spherical Torus Experiment (NSTX), a medium-size spherical tokamak with a compact divertor, and DIII-D, a large conventional aspect ratio tokamak, demonstrate that the snowflake (SF) divertor configuration (D.D. Ryutov, Phys. Plasmas, 14, 064502, 2007) may provide a promising solution for mitigating divertor heat loads and target plate erosion compatible with core H-mode confinement in future fusion devices, where the standard radiative divertor solution may be inadequate. In NSTX, where the initial high-power SF experiment were performed, the SF divertor was compatible with H-mode confinement, and led to the destabilization of large ELMs. However, a stable partial detachment of the outer strike point was also achieved where inter-ELM peak heat flux was reduced by factors 3-5, and peak ELM heat flux was reduced by up to 80% (cf. standard divertor). The DIII-D studies show the SF divertor enables significant power spreading in attached and radiative divertor conditions. Results include: compatibility with the core and pedestal, peak inter-ELM divertor heat flux reduction due to geometry at lower ne, and ELM energy and divertor peak heat flux reduction, especially prominent in radiative D2-seeded SF divertor, and nearly complete power detachment and broader radiated power distribution in the radiative D2-seeded SF divertor at PSOL = 3-4 MW. A variety of SF configurations can be supported by the divertor coil set in NSTX Upgrade. Edge transport modeling with the multi-fluid edge transport code UEDGE shows that the radiative SF divertor can successfully reduce peak divertor heat flux for the projected PSOL ≃ 9 MW case. The radiative SF divertor with carbon impurity provides a wider ne operating window, 50% less argon is needed in the impurity-seeded SF configuration to achieve similar qpeak reduction factors (cf. standard divertor).

UR - https://www.scopus.com/pages/publications/84978924575

UR - https://www.scopus.com/pages/publications/84978924575#tab=citedBy

U2 - 10.1109/SOFE.2015.7482263

DO - 10.1109/SOFE.2015.7482263

M3 - Conference contribution

T3 - Proceedings - Symposium on Fusion Engineering

BT - 2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015

PB - Institute of Electrical and Electronics Engineers Inc.

T2 - 26th IEEE Symposium on Fusion Engineering, SOFE 2015

Y2 - 31 May 2015 through 4 June 2015

ER -

Soukhanovskii VA, Allen SL, Fenstermacher ME, Lasnier CJ, Makowski MA, McLean AG et al. Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution. In 2015 IEEE 26th Symposium on Fusion Engineering, SOFE 2015. Institute of Electrical and Electronics Engineers Inc. 2016. 7482263. (Proceedings - Symposium on Fusion Engineering). doi: 10.1109/SOFE.2015.7482263

Developing snowflake divertor physics basis in the DIII-D, NSTX and NSTX-U tokamaks aimed at the divertor power exhaust solution.

Abstract

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ASJC Scopus subject areas

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