Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years

Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall intera...

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Veröffentlicht in:Journal of fusion energy 2021-06, Vol.40 (1), p.3, Article 3
Hauptverfasser: Wang, L., Xu, G. S., Hu, J. S., Li, K. D., Yuan, Q. P., Liu, J. B., Ding, F., Yu, Y. W., Luo, Z. P., Xu, J. C., Meng, L. Y., Wu, K., Zhang, B., Chen, M. W., Deng, G. Z., Liu, X. J., Yang, Z. S., Liu, X., Liu, S. C., Ding, R., Zuo, G. Z., Sun, Z., Wu, J. H., Cao, B., Zhang, Y., Duan, Y. M., Zhang, L., Qian, X. Y., Li, A., Chen, L., Jia, M. N., Si, H., Xia, T. Y., Sun, Y. W., Chen, Y. P., Li, Q., Luo, G. N., Yao, D. M., Xiao, B. J., Gong, X. Z., Zhang, X. D., Wan, B. N., Wang, H. Q., Guo, H. Y., Eldon, D., Garofalo, A. M., Liang, Y., Xu, S., Sang, C. F., Wang, D. Z., Dai, S. Y., Sun, J. Z., Ding, H. B., Maingi, R., Gan, K. F., Zou, X. L., Du, H. L.
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container_issue 1
container_start_page 3
container_title Journal of fusion energy
container_volume 40
creator Wang, L.
Xu, G. S.
Hu, J. S.
Li, K. D.
Yuan, Q. P.
Liu, J. B.
Ding, F.
Yu, Y. W.
Luo, Z. P.
Xu, J. C.
Meng, L. Y.
Wu, K.
Zhang, B.
Chen, M. W.
Deng, G. Z.
Liu, X. J.
Yang, Z. S.
Liu, X.
Liu, S. C.
Ding, R.
Zuo, G. Z.
Sun, Z.
Wu, J. H.
Cao, B.
Zhang, Y.
Duan, Y. M.
Zhang, L.
Qian, X. Y.
Li, A.
Chen, L.
Jia, M. N.
Si, H.
Xia, T. Y.
Sun, Y. W.
Chen, Y. P.
Li, Q.
Luo, G. N.
Yao, D. M.
Xiao, B. J.
Gong, X. Z.
Zhang, X. D.
Wan, B. N.
Wang, H. Q.
Guo, H. Y.
Eldon, D.
Garofalo, A. M.
Liang, Y.
Xu, S.
Sang, C. F.
Wang, D. Z.
Dai, S. Y.
Sun, J. Z.
Ding, H. B.
Maingi, R.
Gan, K. F.
Zou, X. L.
Du, H. L.
description Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. We have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. A brief near-term plan on the integrated control of divertor plasma-wall interactions in long-time scale will also be introduced, aiming to provide favorable divertor operation solution for ITER and CFETR.
doi_str_mv 10.1007/s10894-021-00290-9
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S. ; Hu, J. S. ; Li, K. D. ; Yuan, Q. P. ; Liu, J. B. ; Ding, F. ; Yu, Y. W. ; Luo, Z. P. ; Xu, J. C. ; Meng, L. Y. ; Wu, K. ; Zhang, B. ; Chen, M. W. ; Deng, G. Z. ; Liu, X. J. ; Yang, Z. S. ; Liu, X. ; Liu, S. C. ; Ding, R. ; Zuo, G. Z. ; Sun, Z. ; Wu, J. H. ; Cao, B. ; Zhang, Y. ; Duan, Y. M. ; Zhang, L. ; Qian, X. Y. ; Li, A. ; Chen, L. ; Jia, M. N. ; Si, H. ; Xia, T. Y. ; Sun, Y. W. ; Chen, Y. P. ; Li, Q. ; Luo, G. N. ; Yao, D. M. ; Xiao, B. J. ; Gong, X. Z. ; Zhang, X. D. ; Wan, B. N. ; Wang, H. Q. ; Guo, H. Y. ; Eldon, D. ; Garofalo, A. M. ; Liang, Y. ; Xu, S. ; Sang, C. F. ; Wang, D. Z. ; Dai, S. Y. ; Sun, J. Z. ; Ding, H. B. ; Maingi, R. ; Gan, K. F. ; Zou, X. L. ; Du, H. L.</creator><creatorcontrib>Wang, L. ; Xu, G. S. ; Hu, J. S. ; Li, K. D. ; Yuan, Q. P. ; Liu, J. B. ; Ding, F. ; Yu, Y. W. ; Luo, Z. P. ; Xu, J. C. ; Meng, L. Y. ; Wu, K. ; Zhang, B. ; Chen, M. W. ; Deng, G. Z. ; Liu, X. J. ; Yang, Z. S. ; Liu, X. ; Liu, S. C. ; Ding, R. ; Zuo, G. Z. ; Sun, Z. ; Wu, J. H. ; Cao, B. ; Zhang, Y. ; Duan, Y. M. ; Zhang, L. ; Qian, X. Y. ; Li, A. ; Chen, L. ; Jia, M. N. ; Si, H. ; Xia, T. Y. ; Sun, Y. W. ; Chen, Y. P. ; Li, Q. ; Luo, G. N. ; Yao, D. M. ; Xiao, B. J. ; Gong, X. Z. ; Zhang, X. D. ; Wan, B. N. ; Wang, H. Q. ; Guo, H. Y. ; Eldon, D. ; Garofalo, A. M. ; Liang, Y. ; Xu, S. ; Sang, C. F. ; Wang, D. Z. ; Dai, S. Y. ; Sun, J. Z. ; Ding, H. B. ; Maingi, R. ; Gan, K. F. ; Zou, X. L. ; Du, H. L. ; Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)</creatorcontrib><description>Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. We have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. 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(PPPL), Princeton, NJ (United States)</creatorcontrib><title>Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years</title><title>Journal of fusion energy</title><addtitle>J Fusion Energ</addtitle><description>Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. We have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. A brief near-term plan on the integrated control of divertor plasma-wall interactions in long-time scale will also be introduced, aiming to provide favorable divertor operation solution for ITER and CFETR.</description><subject>1st China Fusion Energy Conference – Part II</subject><subject>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</subject><subject>Active control</subject><subject>Cooling</subject><subject>divertor</subject><subject>EAST</subject><subject>Electrons</subject><subject>Energy Systems</subject><subject>Feedback control</subject><subject>Fusion reactors</subject><subject>Heat flux</subject><subject>Impurities</subject><subject>Nuclear Energy</subject><subject>Nuclear Fusion</subject><subject>Nuclear power plants</subject><subject>Original Research</subject><subject>particle exhaust</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Plasma</subject><subject>Plasma equilibrium</subject><subject>Plasma Physics</subject><subject>Radiation</subject><subject>Simulation</subject><subject>Steady state</subject><subject>Superconductors</subject><subject>Sustainable Development</subject><subject>Tokamak devices</subject><subject>Tokamaks</subject><subject>Topology</subject><issn>0164-0313</issn><issn>1572-9591</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><sourceid>AFKRA</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><recordid>eNp9kc9rVDEQxx-i4Fr9BzwFPb86Sd6P5LisrRUWWth68BRmk3nblNdkTbKl_e9NfYI3mcPAzOczDHyb5iOHcw4wfskclO5aELwFEBpa_apZ8X4Ure41f92sgA91Lbl827zL-R4AtOr0qik3KR4S5czixL76R0olJnZFWBgGx24wFW9nYpfz6YltYigpzswHdrHe3bKpomv3iMGSY7tC6J7bXcFC7PpICYuP4YUtd8S2mAvjwH4Spvy-eTPhnOnD337W_Li8uN1ctdvrb983621ru0GVVqNQAonGSVo9oEM1jVZwEOD2TknUgsthdIgKySLJ3hHCvgfnhr1yrpdnzaflbszFm2x9IXtnYwhki-GKKzmqCn1eoGOKv06Ui7mPpxTqX0boioASPa_U-UIdcCbjwxRLQlvL0YOvJ2nydb4eedfpoRpVEItgU8w50WSOyT9gejYczEtmZsnM1MzMn8yMrpJcpFzhcKD075f_WL8BIMWY8g</recordid><startdate>20210601</startdate><enddate>20210601</enddate><creator>Wang, L.</creator><creator>Xu, G. 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L.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c468t-9a282aee7f3c96ada8f7c21020dbd83a921367daa8aecae35dea0b50dd6b8dd53</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>1st China Fusion Energy Conference – Part II</topic><topic>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</topic><topic>Active control</topic><topic>Cooling</topic><topic>divertor</topic><topic>EAST</topic><topic>Electrons</topic><topic>Energy Systems</topic><topic>Feedback control</topic><topic>Fusion reactors</topic><topic>Heat flux</topic><topic>Impurities</topic><topic>Nuclear Energy</topic><topic>Nuclear Fusion</topic><topic>Nuclear power plants</topic><topic>Original Research</topic><topic>particle exhaust</topic><topic>Physics</topic><topic>Physics and Astronomy</topic><topic>Plasma</topic><topic>Plasma equilibrium</topic><topic>Plasma Physics</topic><topic>Radiation</topic><topic>Simulation</topic><topic>Steady state</topic><topic>Superconductors</topic><topic>Sustainable Development</topic><topic>Tokamak devices</topic><topic>Tokamaks</topic><topic>Topology</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Wang, L.</creatorcontrib><creatorcontrib>Xu, G. S.</creatorcontrib><creatorcontrib>Hu, J. S.</creatorcontrib><creatorcontrib>Li, K. D.</creatorcontrib><creatorcontrib>Yuan, Q. P.</creatorcontrib><creatorcontrib>Liu, J. B.</creatorcontrib><creatorcontrib>Ding, F.</creatorcontrib><creatorcontrib>Yu, Y. W.</creatorcontrib><creatorcontrib>Luo, Z. P.</creatorcontrib><creatorcontrib>Xu, J. C.</creatorcontrib><creatorcontrib>Meng, L. Y.</creatorcontrib><creatorcontrib>Wu, K.</creatorcontrib><creatorcontrib>Zhang, B.</creatorcontrib><creatorcontrib>Chen, M. W.</creatorcontrib><creatorcontrib>Deng, G. Z.</creatorcontrib><creatorcontrib>Liu, X. J.</creatorcontrib><creatorcontrib>Yang, Z. S.</creatorcontrib><creatorcontrib>Liu, X.</creatorcontrib><creatorcontrib>Liu, S. C.</creatorcontrib><creatorcontrib>Ding, R.</creatorcontrib><creatorcontrib>Zuo, G. Z.</creatorcontrib><creatorcontrib>Sun, Z.</creatorcontrib><creatorcontrib>Wu, J. H.</creatorcontrib><creatorcontrib>Cao, B.</creatorcontrib><creatorcontrib>Zhang, Y.</creatorcontrib><creatorcontrib>Duan, Y. M.</creatorcontrib><creatorcontrib>Zhang, L.</creatorcontrib><creatorcontrib>Qian, X. Y.</creatorcontrib><creatorcontrib>Li, A.</creatorcontrib><creatorcontrib>Chen, L.</creatorcontrib><creatorcontrib>Jia, M. N.</creatorcontrib><creatorcontrib>Si, H.</creatorcontrib><creatorcontrib>Xia, T. Y.</creatorcontrib><creatorcontrib>Sun, Y. W.</creatorcontrib><creatorcontrib>Chen, Y. P.</creatorcontrib><creatorcontrib>Li, Q.</creatorcontrib><creatorcontrib>Luo, G. N.</creatorcontrib><creatorcontrib>Yao, D. M.</creatorcontrib><creatorcontrib>Xiao, B. J.</creatorcontrib><creatorcontrib>Gong, X. Z.</creatorcontrib><creatorcontrib>Zhang, X. D.</creatorcontrib><creatorcontrib>Wan, B. N.</creatorcontrib><creatorcontrib>Wang, H. Q.</creatorcontrib><creatorcontrib>Guo, H. Y.</creatorcontrib><creatorcontrib>Eldon, D.</creatorcontrib><creatorcontrib>Garofalo, A. M.</creatorcontrib><creatorcontrib>Liang, Y.</creatorcontrib><creatorcontrib>Xu, S.</creatorcontrib><creatorcontrib>Sang, C. F.</creatorcontrib><creatorcontrib>Wang, D. Z.</creatorcontrib><creatorcontrib>Dai, S. Y.</creatorcontrib><creatorcontrib>Sun, J. Z.</creatorcontrib><creatorcontrib>Ding, H. B.</creatorcontrib><creatorcontrib>Maingi, R.</creatorcontrib><creatorcontrib>Gan, K. F.</creatorcontrib><creatorcontrib>Zou, X. L.</creatorcontrib><creatorcontrib>Du, H. L.</creatorcontrib><creatorcontrib>Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)</creatorcontrib><collection>CrossRef</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>Materials Science &amp; Engineering Collection</collection><collection>ProQuest Central UK/Ireland</collection><collection>Advanced Technologies &amp; Aerospace Collection</collection><collection>ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central Korea</collection><collection>SciTech Premium Collection</collection><collection>ProQuest Engineering Collection</collection><collection>Engineering Database</collection><collection>Advanced Technologies &amp; Aerospace Database</collection><collection>ProQuest Advanced Technologies &amp; Aerospace Collection</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>Engineering Collection</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><jtitle>Journal of fusion energy</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Wang, L.</au><au>Xu, G. S.</au><au>Hu, J. S.</au><au>Li, K. D.</au><au>Yuan, Q. P.</au><au>Liu, J. B.</au><au>Ding, F.</au><au>Yu, Y. W.</au><au>Luo, Z. P.</au><au>Xu, J. C.</au><au>Meng, L. Y.</au><au>Wu, K.</au><au>Zhang, B.</au><au>Chen, M. W.</au><au>Deng, G. Z.</au><au>Liu, X. J.</au><au>Yang, Z. S.</au><au>Liu, X.</au><au>Liu, S. C.</au><au>Ding, R.</au><au>Zuo, G. Z.</au><au>Sun, Z.</au><au>Wu, J. H.</au><au>Cao, B.</au><au>Zhang, Y.</au><au>Duan, Y. M.</au><au>Zhang, L.</au><au>Qian, X. Y.</au><au>Li, A.</au><au>Chen, L.</au><au>Jia, M. N.</au><au>Si, H.</au><au>Xia, T. Y.</au><au>Sun, Y. W.</au><au>Chen, Y. P.</au><au>Li, Q.</au><au>Luo, G. N.</au><au>Yao, D. M.</au><au>Xiao, B. J.</au><au>Gong, X. Z.</au><au>Zhang, X. D.</au><au>Wan, B. N.</au><au>Wang, H. Q.</au><au>Guo, H. Y.</au><au>Eldon, D.</au><au>Garofalo, A. M.</au><au>Liang, Y.</au><au>Xu, S.</au><au>Sang, C. F.</au><au>Wang, D. Z.</au><au>Dai, S. Y.</au><au>Sun, J. Z.</au><au>Ding, H. B.</au><au>Maingi, R.</au><au>Gan, K. F.</au><au>Zou, X. L.</au><au>Du, H. L.</au><aucorp>Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years</atitle><jtitle>Journal of fusion energy</jtitle><stitle>J Fusion Energ</stitle><date>2021-06-01</date><risdate>2021</risdate><volume>40</volume><issue>1</issue><spage>3</spage><pages>3-</pages><artnum>3</artnum><issn>0164-0313</issn><eissn>1572-9591</eissn><abstract>Active control of the excessively high heat and particle fluxes on the divertor target plates is of fundamental importance to the steady state operation of tokamaks, especially for fusion reactors. A series of experiments have been carried out on this critical issue to relieve the plasma-wall interactions in the experimental advanced superconducting tokamak (EAST) in the last ten years, not only contributing to the long pulse operation of EAST itself, but also providing physical understandings and potential techniques to the next-generation devices like ITER. We have characterized the power deposition pattern and broadened the divertor footprint width effectively. The plasma-wetted area is actively handled using either 3-dimentional edge magnetic topology or advanced plasma equilibrium, thereby peak heat flux around the strike point is reduced. Active control of detachment or radiation compatible with core plasma performance has progressed significantly in very recent years, with a series of active feedback control modules developed and utilized successfully, based on the divertor physics advances with both experiments and simulation. The upper divertor of EAST was upgraded from graphite to active water-cooling ITER-like tungsten in 2014, exhibiting much enhanced heat removal capability. As for the particle exhaust including both fueling and impurity particles, in addition to wall conditioning and impurity source control, the efficiency of particle flux exhaust is optimized by making full use of the divertor closure and the plasma drifts in both scrape-off layer and divertor volume. These heat and particle exhaust advances contribute greatly to a series of EAST achievements like H-mode operation over 100 s. A brief near-term plan on the integrated control of divertor plasma-wall interactions in long-time scale will also be introduced, aiming to provide favorable divertor operation solution for ITER and CFETR.</abstract><cop>New York</cop><pub>Springer US</pub><doi>10.1007/s10894-021-00290-9</doi><oa>free_for_read</oa></addata></record>
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subjects 1st China Fusion Energy Conference – Part II
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Active control
Cooling
divertor
EAST
Electrons
Energy Systems
Feedback control
Fusion reactors
Heat flux
Impurities
Nuclear Energy
Nuclear Fusion
Nuclear power plants
Original Research
particle exhaust
Physics
Physics and Astronomy
Plasma
Plasma equilibrium
Plasma Physics
Radiation
Simulation
Steady state
Superconductors
Sustainable Development
Tokamak devices
Tokamaks
Topology
title Progress of Divertor Heat and Particle Flux Control in EAST for Advanced Steady-State Operation in the Last 10 Years
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