Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST

Wang, L.; Guo, H. Y.; Ding, F.; Yu, Y. W.; Yuan, Q. P.; Xu, G. S.; Wang, H. Q.; Zhang, L.; Ding, R.; Xu, J. C.; Liu, J. B.; Zhang, B.; Wu, K.; Li, K. D.; Duan, Y. M.; Luo, Z. P.; Wu, J. H.; Zuo, G. Z.; Sun, Z.; Eldon, D.; Leonard, A. W.; Petrie, T.; Hyatt, A.; Humphreys, D.; Thomas, D.; Yang, Z. S.; Chen, X. H.; Feng, W.; Chen, L.; Meng, L. Y.; Qian, X. Y.; Liang, Y.; Sang, C. F.; Xiao, B. J.; Luo, G. -N.; Hu, J. S.; Maingi, R.; Zou, X. L.; Qian, J. P.; Gong, X. Z.; Garofalo, A. M.; Li, J.; Wan, B. N.

doi:10.1088/1741-4326/ab1ed4

Title: Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST

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Abstract

A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which has steady-state power exhaust capability of 10 MWm^–2. The peak temperature of W target saturated at 12 s to the value T ~ 500 °C with a heat flux ~3.3 MW m^–2 being maintained during the discharge. By tailoring the 3D divertor plasma footprint through edge magnetic topology change, the heat load was broadly dispersed and thus peak heat flux and W sputtering were well controlled. Active feedback control of H-mode detachment with D₂ fuelling or divertor impurity seeding has been achieved successfully, with excellent compatibility with the core plasma performance. Active feedback control of radiative power utilizing neon seeding was achieved with f_rad = 18%–41% in H-mode operation, exhibiting potential for heat flux reduction with divertor and edge radiation. This has been further demonstrated in DIII-D high β _P H-mode scenario within the joint DIII-D/EAST experiment using impurity seeding from the divertor volume. Steady-state particle control and impurity exhaust has been achieved for long pulse H-mode operation over 100 s with the W divertor by leveraging the effect of driftsmore »« less

Publication Date:: Thu Jul 04 00:00:00 EDT 2019

Research Org.:: Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE; National Key Research and Development Program of China; National Natural Science Foundation of China (NSFC); National Magnetic Confinement Fusion Science Program of China; Key Research Program of Frontier Sciences; K.C. Wong Education Foundation

Contributing Org.:: the EAST team

OSTI Identifier:: 1545306

Grant/Contract Number:: FC02-04ER546981

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:: 43 PARTICLE ACCELERATORS; divertor; plasma-wall interaction; power and particle exhaust; tungsten sputtering; EAST

Citation Formats


                    Wang, L., Guo, H. Y., Ding, F., Yu, Y. W., Yuan, Q. P., Xu, G. S., Wang, H. Q., Zhang, L., Ding, R., Xu, J. C., Liu, J. B., Zhang, B., Wu, K., Li, K. D., Duan, Y. M., Luo, Z. P., Wu, J. H., Zuo, G. Z., Sun, Z., Eldon, D., Leonard, A. W., Petrie, T., Hyatt, A., Humphreys, D., Thomas, D., Yang, Z. S., Chen, X. H., Feng, W., Chen, L., Meng, L. Y., Qian, X. Y., Liang, Y., Sang, C. F., Xiao, B. J., Luo, G. -N., Hu, J. S., Maingi, R., Zou, X. L., Qian, J. P., Gong, X. Z., Garofalo, A. M., Li, J., and Wan, B. N. Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST.  United States: N. p., 2019. 
Web.  doi:10.1088/1741-4326/ab1ed4.

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                    Wang, L., Guo, H. Y., Ding, F., Yu, Y. W., Yuan, Q. P., Xu, G. S., Wang, H. Q., Zhang, L., Ding, R., Xu, J. C., Liu, J. B., Zhang, B., Wu, K., Li, K. D., Duan, Y. M., Luo, Z. P., Wu, J. H., Zuo, G. Z., Sun, Z., Eldon, D., Leonard, A. W., Petrie, T., Hyatt, A., Humphreys, D., Thomas, D., Yang, Z. S., Chen, X. H., Feng, W., Chen, L., Meng, L. Y., Qian, X. Y., Liang, Y., Sang, C. F., Xiao, B. J., Luo, G. -N., Hu, J. S., Maingi, R., Zou, X. L., Qian, J. P., Gong, X. Z., Garofalo, A. M., Li, J., & Wan, B. N. Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST.  United States.  https://doi.org/10.1088/1741-4326/ab1ed4

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                    Wang, L., Guo, H. Y., Ding, F., Yu, Y. W., Yuan, Q. P., Xu, G. S., Wang, H. Q., Zhang, L., Ding, R., Xu, J. C., Liu, J. B., Zhang, B., Wu, K., Li, K. D., Duan, Y. M., Luo, Z. P., Wu, J. H., Zuo, G. Z., Sun, Z., Eldon, D., Leonard, A. W., Petrie, T., Hyatt, A., Humphreys, D., Thomas, D., Yang, Z. S., Chen, X. H., Feng, W., Chen, L., Meng, L. Y., Qian, X. Y., Liang, Y., Sang, C. F., Xiao, B. J., Luo, G. -N., Hu, J. S., Maingi, R., Zou, X. L., Qian, J. P., Gong, X. Z., Garofalo, A. M., Li, J., and Wan, B. N. Thu .  
"Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST".  United States.  https://doi.org/10.1088/1741-4326/ab1ed4.  https://www.osti.gov/servlets/purl/1545306.

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@article{osti_1545306,

  title        = {Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST},

  author       = {Wang, L. and Guo, H. Y. and Ding, F. and Yu, Y. W. and Yuan, Q. P. and Xu, G. S. and Wang, H. Q. and Zhang, L. and Ding, R. and Xu, J. C. and Liu, J. B. and Zhang, B. and Wu, K. and Li, K. D. and Duan, Y. M. and Luo, Z. P. and Wu, J. H. and Zuo, G. Z. and Sun, Z. and Eldon, D. and Leonard, A. W. and Petrie, T. and Hyatt, A. and Humphreys, D. and Thomas, D. and Yang, Z. S. and Chen, X. H. and Feng, W. and Chen, L. and Meng, L. Y. and Qian, X. Y. and Liang, Y. and Sang, C. F. and Xiao, B. J. and Luo, G. -N. and Hu, J. S. and Maingi, R. and Zou, X. L. and Qian, J. P. and Gong, X. Z. and Garofalo, A. M. and Li, J. and Wan, B. N.},

  abstractNote = {A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which has steady-state power exhaust capability of 10 MWm–2. The peak temperature of W target saturated at 12 s to the value T ~ 500 °C with a heat flux ~3.3 MW m–2 being maintained during the discharge. By tailoring the 3D divertor plasma footprint through edge magnetic topology change, the heat load was broadly dispersed and thus peak heat flux and W sputtering were well controlled. Active feedback control of H-mode detachment with D2 fuelling or divertor impurity seeding has been achieved successfully, with excellent compatibility with the core plasma performance. Active feedback control of radiative power utilizing neon seeding was achieved with frad = 18%–41% in H-mode operation, exhibiting potential for heat flux reduction with divertor and edge radiation. This has been further demonstrated in DIII-D high β P H-mode scenario within the joint DIII-D/EAST experiment using impurity seeding from the divertor volume. Steady-state particle control and impurity exhaust has been achieved for long pulse H-mode operation over 100 s with the W divertor by leveraging the effect of drifts and optimized divertor configuration, coupled with strong pumping and extensive wall conditioning. Methods toward the reduction of divertor W sourcing, which is of crucial importance for a metal-wall tokamak, are also explored. These advances provide vital experimental information on favourable core-edge integration for high power, long-pulse H-mode operation in EAST, ITER and CFETR.},

  doi          = {10.1088/1741-4326/ab1ed4},

  journal      = {Nuclear Fusion},

  number       = 8,

  volume       = 59,

  place        = {United States},

  year         = {Thu Jul 04 00:00:00 EDT 2019},

  month        = {Thu Jul 04 00:00:00 EDT 2019}

}

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