Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak

Gong, X.; Garofalo, A. M.; Huang, J.; Qian, J.; Holcomb, C. T.; Ekedah, A.; Maingi, R.; Li, E.; Zeng, L.; Zhang, B.; Chen, J.; Wu, M.; Du, H.; Li, M.; Zhu, X.; Sun, Y.; Xu, G.; Zang, Q.; Wang, L.; Zhang, L.; Liu, H.; Lyu, B.; Sun, P.; Ding, S.; Zhang, X.; Liu, F.; Zhao, Y.; Xiao, B.; Hu, J.; Hu, C.; Hu, L.; Li, J.; Wan, B.

doi:10.1088/1741-4326/ab1c7b

Title: Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak

Abstract

Recent Experimental Advanced Superconducting Tokamak (EAST) experiments have successfully demonstrated a long-pulse steady-state scenario with improved plasma performance through integrated operation since the last IAEA FEC in 2016. A discharge with a duration over 100 s using pure radio frequency (RF) power heating and current drive has been obtained with the required characteristics for future long-pulse tokamak reactors such as good energy confinement quality (H_98y2 ~ 1.1) with electron internal transport barrier inside ρ < 0.4, small ELMs (frequency ~100–200 Hz), and good control of impurity and heat exhaust with the tungsten divertor. The optimization of X-point, plasma shape, the outer gap and local gas puffing near the low hybrid wave (LHW) antenna were integrated with global parameters of BT and line-averaged electron density for higher current drive efficiency of LHW and on-axis deposition of electron cyclotron heating in the long-pulse operation. More recently, a high βP RF-only discharge (β_P ~ 1.9 and β_N ~ 1.5, $$\langle$$n_e$$\rangle$$/n_GW ~ 0.80, f_bs ~ 45% at q₉₅ ~ 6.8) was successfully maintained over 24 s with improved hardware capabilities, demonstrating performance levels needed for the China Fusion Engineering Test Reactor steady-state operation. In this work, a higher energy confinement is observed at higher β_P and with favorable toroidal field direction. Towards the next goal (≥400 s long-pulse H-mode operations with ~50% bootstrap current fraction) on EAST, an integrated control of the current density profile, pressure profile and radiated divertor will be addressed in the near future.

Authors:

Gong, X. ^[1];

^[2]; Huang, J. ^[1]; Qian, J. ^[1]; Holcomb, C. T. ^[3]; Ekedah, A. ^[4]; Maingi, R. ^[5]; Li, E. ^[1];

^[1]; Zhang, B. ^[1];

^[1];

^[1]; Du, H. ^[1];

^[1]; Zhu, X. ^[1];

^[1]; Xu, G. ^[1]; Zang, Q. ^[1]; Wang, L. ^[1]; Zhang, L. ^[1] more »

Chinese Academy of Sciences (CAS), Hefei (China). Institute of Plasma Physics
General Atomics, San Diego, CA (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Alternative Energies and Atomic Energy Commission (CEA), Saint Paul-lez-Durance (France)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Publication Date:: Mon Jul 01 00:00:00 EDT 2019

Research Org.:: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA); National Magnetic Confinement Fusion Program of China; Chinese Academy of Sciences (CAS); National Key Research and Development Program of China; National Natural Science Foundation of China (NSFC); National Nature Science Foundation of China

Contributing Org.:: EAST Team

OSTI Identifier:: 1798017

Alternate Identifier(s):: OSTI ID: 1511460

Report Number(s):: LLNL-JRNL-777065
Journal ID: ISSN 0029-5515; 966470; TRN: US2210645

Grant/Contract Number:: AC52-07NA27344

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Fusion

Additional Journal Information:: Journal Volume: 59; Journal Issue: 8; Journal ID: ISSN 0029-5515

Publisher:: IOP Science

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats


                    Gong, X., Garofalo, A. M., Huang, J., Qian, J., Holcomb, C. T., Ekedah, A., Maingi, R., Li, E., Zeng, L., Zhang, B., Chen, J., Wu, M., Du, H., Li, M., Zhu, X., Sun, Y., Xu, G., Zang, Q., Wang, L., Zhang, L., Liu, H., Lyu, B., Sun, P., Ding, S., Zhang, X., Liu, F., Zhao, Y., Xiao, B., Hu, J., Hu, C., Hu, L., Li, J., and Wan, B. Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak.  United States: N. p., 2019. 
Web.  doi:10.1088/1741-4326/ab1c7b.

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                    Gong, X., Garofalo, A. M., Huang, J., Qian, J., Holcomb, C. T., Ekedah, A., Maingi, R., Li, E., Zeng, L., Zhang, B., Chen, J., Wu, M., Du, H., Li, M., Zhu, X., Sun, Y., Xu, G., Zang, Q., Wang, L., Zhang, L., Liu, H., Lyu, B., Sun, P., Ding, S., Zhang, X., Liu, F., Zhao, Y., Xiao, B., Hu, J., Hu, C., Hu, L., Li, J., & Wan, B. Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak.  United States.  https://doi.org/10.1088/1741-4326/ab1c7b

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                    Gong, X., Garofalo, A. M., Huang, J., Qian, J., Holcomb, C. T., Ekedah, A., Maingi, R., Li, E., Zeng, L., Zhang, B., Chen, J., Wu, M., Du, H., Li, M., Zhu, X., Sun, Y., Xu, G., Zang, Q., Wang, L., Zhang, L., Liu, H., Lyu, B., Sun, P., Ding, S., Zhang, X., Liu, F., Zhao, Y., Xiao, B., Hu, J., Hu, C., Hu, L., Li, J., and Wan, B. Mon .  
"Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak".  United States.  https://doi.org/10.1088/1741-4326/ab1c7b.  https://www.osti.gov/servlets/purl/1798017.

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@article{osti_1798017,

  title        = {Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak},

  author       = {Gong, X. and Garofalo, A. M. and Huang, J. and Qian, J. and Holcomb, C. T. and Ekedah, A. and Maingi, R. and Li, E. and Zeng, L. and Zhang, B. and Chen, J. and Wu, M. and Du, H. and Li, M. and Zhu, X. and Sun, Y. and Xu, G. and Zang, Q. and Wang, L. and Zhang, L. and Liu, H. and Lyu, B. and Sun, P. and Ding, S. and Zhang, X. and Liu, F. and Zhao, Y. and Xiao, B. and Hu, J. and Hu, C. and Hu, L. and Li, J. and Wan, B.},

  abstractNote = {Recent Experimental Advanced Superconducting Tokamak (EAST) experiments have successfully demonstrated a long-pulse steady-state scenario with improved plasma performance through integrated operation since the last IAEA FEC in 2016. A discharge with a duration over 100 s using pure radio frequency (RF) power heating and current drive has been obtained with the required characteristics for future long-pulse tokamak reactors such as good energy confinement quality (H98y2 ~ 1.1) with electron internal transport barrier inside ρ < 0.4, small ELMs (frequency ~100–200 Hz), and good control of impurity and heat exhaust with the tungsten divertor. The optimization of X-point, plasma shape, the outer gap and local gas puffing near the low hybrid wave (LHW) antenna were integrated with global parameters of BT and line-averaged electron density for higher current drive efficiency of LHW and on-axis deposition of electron cyclotron heating in the long-pulse operation. More recently, a high βP RF-only discharge (βP ~ 1.9 and βN ~ 1.5, $\langle$ne$\rangle$/nGW ~ 0.80, fbs ~ 45% at q95 ~ 6.8) was successfully maintained over 24 s with improved hardware capabilities, demonstrating performance levels needed for the China Fusion Engineering Test Reactor steady-state operation. In this work, a higher energy confinement is observed at higher βP and with favorable toroidal field direction. Towards the next goal (≥400 s long-pulse H-mode operations with ~50% bootstrap current fraction) on EAST, an integrated control of the current density profile, pressure profile and radiated divertor will be addressed in the near future.},

  doi          = {10.1088/1741-4326/ab1c7b},

  journal      = {Nuclear Fusion},

  number       = 8,

  volume       = 59,

  place        = {United States},

  year         = {Mon Jul 01 00:00:00 EDT 2019},

  month        = {Mon Jul 01 00:00:00 EDT 2019}

}

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Journal Article:

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https://doi.org/10.1088/1741-4326/ab1c7b

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Cited by: 48 works

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Figures / Tables:

Figure 1: The new tungsten guide limiter of 4.6GHz LHW antenna

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Works referenced in this record:

Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak
journal, August 2017

Zhang, L.; Morita, S.; Xu, Z.
Nuclear Materials and Energy, Vol. 12
DOI: 10.1016/j.nme.2017.01.009

SOL effects on the pedestal structure in DIII-D discharges
journal, May 2017

Sontag, A. C.; Chen, X.; Canik, J.
Nuclear Fusion, Vol. 57, Issue 7
DOI: 10.1088/1741-4326/aa6cb6

Realization of minute-long steady-state H-mode discharges on EAST
journal, February 2017

Gong, Xianzu; Wan, Baonian; Li, Jiangang
Plasma Science and Technology, Vol. 19, Issue 3
DOI: 10.1088/2058-6272/19/3/032001

A digital long pulse integrator for EAST Tokamak
journal, May 2014

Wang, Y.; Ji, Z. S.; Xu, G. J.
Fusion Engineering and Design, Vol. 89, Issue 5
DOI: 10.1016/j.fusengdes.2014.02.019

Separation of β̄ _p and ℓ _i in tokamaks of non-circular cross-section
journal, October 1985

Lao, L. L.; John, H. St.; Stambaugh, R. D.
Nuclear Fusion, Vol. 25, Issue 10
DOI: 10.1088/0029-5515/25/10/004

Comparison between gas puffing and supersonic molecular beam injection in plasma density feedback experiments in EAST
journal, October 2013

Zheng, Xingwei; Li, Jiangang; Hu, Jiansheng
Plasma Physics and Controlled Fusion, Vol. 55, Issue 11
DOI: 10.1088/0741-3335/55/11/115010

Present Status of the EAST Diagnostics
journal, February 2011

Hu, Liqun
Plasma Science and Technology, Vol. 13, Issue 1
DOI: 10.1088/1009-0630/13/1/25

Progress of the CFETR design
journal, June 2019

Zhuang, G.; Li, G. Q.; Li, J.
Nuclear Fusion, Vol. 59, Issue 11
DOI: 10.1088/1741-4326/ab0e27

Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST
journal, May 2017

Ding, S.; Garofalo, A. M.; Qian, J.
Physics of Plasmas, Vol. 24, Issue 5
DOI: 10.1063/1.4982058

Transport of fast electrons during LHCD in TS, JET, and ASDEX
journal, December 1993

Peysson, Y.
Plasma Physics and Controlled Fusion, Vol. 35, Issue SB
DOI: 10.1088/0741-3335/35/SB/021

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR
journal, November 2017

Garofalo, A. M.; Gong, X. Z.; Ding, S. Y.
Plasma Physics and Controlled Fusion, Vol. 60, Issue 1
DOI: 10.1088/1361-6587/aa8c9d

Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST
journal, June 2017

Garofalo, A. M.; Gong, X. Z.; Qian, J.
Nuclear Fusion, Vol. 57, Issue 7
DOI: 10.1088/1741-4326/aa7186

Works referencing / citing this record:

27th IAEA Fusion Energy Conference: summary of sessions EX/C, EX/S and PPC
journal, January 2020

Campbell, D. J.
Nuclear Fusion, Vol. 60, Issue 2
DOI: 10.1088/1741-4326/ab5cee

Improved high-performance fully non-inductive discharge by optimizing the fast-ion confinement on EAST
journal, October 2019

Huang, J.; Qian, J. P.; Garofalo, A. M.
Nuclear Fusion, Vol. 60, Issue 1
DOI: 10.1088/1741-4326/ab443a

Figures / Tables found in this record:

Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.

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Title: Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak

Abstract

Citation Formats

Figures / Tables:

Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak journal, August 2017

SOL effects on the pedestal structure in DIII-D discharges journal, May 2017

Realization of minute-long steady-state H-mode discharges on EAST journal, February 2017

A digital long pulse integrator for EAST Tokamak journal, May 2014

Separation of β̄ p and ℓ i in tokamaks of non-circular cross-section journal, October 1985

Comparison between gas puffing and supersonic molecular beam injection in plasma density feedback experiments in EAST journal, October 2013

Present Status of the EAST Diagnostics journal, February 2011

Progress of the CFETR design journal, June 2019

Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST journal, May 2017

Transport of fast electrons during LHCD in TS, JET, and ASDEX journal, December 1993

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR journal, November 2017

Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST journal, June 2017

27th IAEA Fusion Energy Conference: summary of sessions EX/C, EX/S and PPC journal, January 2020

Improved high-performance fully non-inductive discharge by optimizing the fast-ion confinement on EAST journal, October 2019

Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak
journal, August 2017

SOL effects on the pedestal structure in DIII-D discharges
journal, May 2017

Realization of minute-long steady-state H-mode discharges on EAST
journal, February 2017

A digital long pulse integrator for EAST Tokamak
journal, May 2014

Separation of β̄ _p and ℓ _i in tokamaks of non-circular cross-section
journal, October 1985

Comparison between gas puffing and supersonic molecular beam injection in plasma density feedback experiments in EAST
journal, October 2013

Present Status of the EAST Diagnostics
journal, February 2011

Progress of the CFETR design
journal, June 2019

Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST
journal, May 2017

Transport of fast electrons during LHCD in TS, JET, and ASDEX
journal, December 1993

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR
journal, November 2017

Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST
journal, June 2017

27th IAEA Fusion Energy Conference: summary of sessions EX/C, EX/S and PPC
journal, January 2020

Improved high-performance fully non-inductive discharge by optimizing the fast-ion confinement on EAST
journal, October 2019