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Divertor heat flux challenge and mitigation in SPARC

Research output: Contribution to journalArticlepeer-review

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Divertor heat flux challenge and mitigation in SPARC. / Kuang, A. Q.; Ballinger, S.; Brunner, D.; Canik, J.; Creely, A. J.; Gray, T.; Greenwald, M.; Hughes, J. W.; Irby, J.; Labombard, B.; Lipschultz, B.; Lore, J. D.; Reinke, M. L.; Terry, J. L.; Umansky, M.; Whyte, D. G.; Wukitch, S.

In: Journal of Plasma Physics, Vol. 86, No. 5, 865860505, 29.09.2020.

Research output: Contribution to journalArticlepeer-review

Harvard

Kuang, AQ, Ballinger, S, Brunner, D, Canik, J, Creely, AJ, Gray, T, Greenwald, M, Hughes, JW, Irby, J, Labombard, B, Lipschultz, B, Lore, JD, Reinke, ML, Terry, JL, Umansky, M, Whyte, DG & Wukitch, S 2020, 'Divertor heat flux challenge and mitigation in SPARC', Journal of Plasma Physics, vol. 86, no. 5, 865860505. https://doi.org/10.1017/S0022377820001117

APA

Kuang, A. Q., Ballinger, S., Brunner, D., Canik, J., Creely, A. J., Gray, T., Greenwald, M., Hughes, J. W., Irby, J., Labombard, B., Lipschultz, B., Lore, J. D., Reinke, M. L., Terry, J. L., Umansky, M., Whyte, D. G., & Wukitch, S. (2020). Divertor heat flux challenge and mitigation in SPARC. Journal of Plasma Physics, 86(5), [865860505]. https://doi.org/10.1017/S0022377820001117

Vancouver

Kuang AQ, Ballinger S, Brunner D, Canik J, Creely AJ, Gray T et al. Divertor heat flux challenge and mitigation in SPARC. Journal of Plasma Physics. 2020 Sep 29;86(5). 865860505. https://doi.org/10.1017/S0022377820001117

Author

Kuang, A. Q. ; Ballinger, S. ; Brunner, D. ; Canik, J. ; Creely, A. J. ; Gray, T. ; Greenwald, M. ; Hughes, J. W. ; Irby, J. ; Labombard, B. ; Lipschultz, B. ; Lore, J. D. ; Reinke, M. L. ; Terry, J. L. ; Umansky, M. ; Whyte, D. G. ; Wukitch, S. / Divertor heat flux challenge and mitigation in SPARC. In: Journal of Plasma Physics. 2020 ; Vol. 86, No. 5.

Bibtex - Download

@article{a9ecc7d5fc504d2ca00a6696194ebea1,
title = "Divertor heat flux challenge and mitigation in SPARC",
abstract = "Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m-2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections (∼11-34 MJ m-2) are comparable with those for ITER. However, the relatively short pulse length (∼25 s pulse, with a ∼10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a ∼1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design. ",
keywords = "fusion plasma, plasma devices",
author = "Kuang, {A. Q.} and S. Ballinger and D. Brunner and J. Canik and Creely, {A. J.} and T. Gray and M. Greenwald and Hughes, {J. W.} and J. Irby and B. Labombard and B. Lipschultz and Lore, {J. D.} and Reinke, {M. L.} and Terry, {J. L.} and M. Umansky and Whyte, {D. G.} and S. Wukitch",
note = "{\textcopyright} The Author(s), 2020.",
year = "2020",
month = sep,
day = "29",
doi = "10.1017/S0022377820001117",
language = "English",
volume = "86",
journal = "Journal of Plasma Physics",
issn = "1469-7807",
publisher = "Cambridge University Press",
number = "5",

}

RIS (suitable for import to EndNote) - Download

TY - JOUR

T1 - Divertor heat flux challenge and mitigation in SPARC

AU - Kuang, A. Q.

AU - Ballinger, S.

AU - Brunner, D.

AU - Canik, J.

AU - Creely, A. J.

AU - Gray, T.

AU - Greenwald, M.

AU - Hughes, J. W.

AU - Irby, J.

AU - Labombard, B.

AU - Lipschultz, B.

AU - Lore, J. D.

AU - Reinke, M. L.

AU - Terry, J. L.

AU - Umansky, M.

AU - Whyte, D. G.

AU - Wukitch, S.

N1 - © The Author(s), 2020.

PY - 2020/9/29

Y1 - 2020/9/29

N2 - Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m-2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections (∼11-34 MJ m-2) are comparable with those for ITER. However, the relatively short pulse length (∼25 s pulse, with a ∼10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a ∼1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.

AB - Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m-2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections (∼11-34 MJ m-2) are comparable with those for ITER. However, the relatively short pulse length (∼25 s pulse, with a ∼10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a ∼1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.

KW - fusion plasma

KW - plasma devices

UR - http://www.scopus.com/inward/record.url?scp=85092282350&partnerID=8YFLogxK

U2 - 10.1017/S0022377820001117

DO - 10.1017/S0022377820001117

M3 - Article

AN - SCOPUS:85092282350

VL - 86

JO - Journal of Plasma Physics

JF - Journal of Plasma Physics

SN - 1469-7807

IS - 5

M1 - 865860505

ER -