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

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 D 2 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 leveragingmore » the effect of drifts and optimized divertor configuration, coupled with strong pumping and extensive wall conditioning. Approaches toward the reduction of divertor W sourcing, which is of crucial importance for a metal-wall tokamak, are also explored. These advances provide important experimental information on favourable core-edge integration for high power, long-pulse H-mode operation in EAST, ITER and CFETR.« less

Authors:
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Publication Date:
Research Org.:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org.:
National Natural Science Foundation of China (NNSFC); The National Magnetic Confinement Fusion Science Program of China; USDOE; The Key Research Program of Frontier Sciences; The K.C. Wong Education Foundation; The Users with Excellence Project of Hefei Science Center CAS
Contributing Org.:
The EAST team
OSTI Identifier:
1532735
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:
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.
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. doi:10.1088/1741-4326/ab1ed4.
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. doi:10.1088/1741-4326/ab1ed4. https://www.osti.gov/servlets/purl/1532735.
@article{osti_1532735,
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. Approaches toward the reduction of divertor W sourcing, which is of crucial importance for a metal-wall tokamak, are also explored. These advances provide important 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 = {2019},
month = {7}
}

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