Improvement on the plasma performances via application of flowing lithium limiters in EAST tokamak

Zuo, G. Z.; Hu, J. S.; Maingi, R.; Li, C. L.; Meng, X. C.; Sun, Z.; Huang, M.; Xu, W.; Qian, Y. Z.; Andruczyk, D.; Tritz, K.; Gong, X. Z.; Li, J. G.

doi:10.1088/1402-4896/ab3bed

Title: Improvement on the plasma performances via application of flowing lithium limiters in EAST tokamak

Journal Article · 26 February 2020 · Physica Scripta

DOI: https://doi.org/10.1088/1402-4896/ab3bed · OSTI ID:1619053

Zuo, G. Z. ^[1]; Hu, J. S. ^[1]; Maingi, R. ^[2]; Li, C. L. ^[3]; Meng, X. C. ^[4];

^[5]; Huang, M. ^[1]; Xu, W. ^[4]; Qian, Y. Z. ^[6]; Andruczyk, D. ^[7]; Tritz, K. ^[8]; Gong, X. Z. ^[1]; Li, J. G. ^[1]

Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics ; Univ. of Science and Technology of China, Hefei (China)
Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics; Shenzhen Univ. (China)
Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics ; Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics; Univ. of Science and Technology of China, Hefei (China)
Univ. of Illinois at Urbana-Champaign, IL (United States)
Johns Hopkins Univ., Baltimore, MD (United States)

Three generation of flowing liquid lithium (FLiLi) limiters have been developed and successfully tested in EAST since 2014. It was confirmed that liquid Li could be driven by an innovative in-vessel DC electromagnetic J × B pump to form a recirculating loop. The FLiLi design was continuously upgraded, resulting in improvement of the liquid Li surface coverage (>80%), elimination of surface erosion, and the increase of heat exhaust capability. Promising results are obtained during FLiLi operations, including a reduction of impurities and recycling to improve plasma confinement, and a mitigation of ELM activity in H-mode plasmas. The FLiLi limiter program has shown basic compatibility with H-mode discharges with auxiliary heating power up to 8.3 MW. These efforts will expand to flowing liquid Li PFC in high heat flux zones, e.g. near the divertor strike point in reactors.

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Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC02-09CH11466; 11775261; 11625524; and 11605246; 2017YFE0301100; 2017YFA0402500

OSTI ID:: 1619053

Journal Information:: Physica Scripta, Vol. T171; ISSN 0031-8949

Publisher:: IOP PublishingCopyright Statement

Country of Publication:: United States

Language:: English

References (20)

Performance projections for the lithium tokamak experiment (LTX) Majeski, R.; Berzak, L.; Gray, T. Nuclear Fusion, Vol. 49, Issue 5 https://doi.org/10.1088/0029-5515/49/5/055014	journal	April 2009
Conference Report on the 4rd International Symposium on Lithium Applications Tabares, F. L.; Hirooka, Y.; Maingi, R. Nuclear Fusion, Vol. 56, Issue 12 https://doi.org/10.1088/0029-5515/56/12/127002	journal	September 2016
Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment Majeski, R.; Bell, R. E.; Boyle, D. P. Physics of Plasmas, Vol. 24, Issue 5 https://doi.org/10.1063/1.4977916	journal	May 2017
Methods and preliminary measurement results of liquid Li wettability Zuo, G. Z.; Hu, J. S.; Ren, J. Review of Scientific Instruments, Vol. 85, Issue 2 https://doi.org/10.1063/1.4865118	journal	February 2014
Effects of large area liquid lithium limiters on spherical torus plasmas Kaita, R.; Majeski, R.; Boaz, M. Journal of Nuclear Materials, Vol. 337-339 https://doi.org/10.1016/j.jnucmat.2004.10.019	journal	March 2005
Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices Mirnov, S. V.; Azizov, E. A.; Evtikhin, V. A. Plasma Physics and Controlled Fusion, Vol. 48, Issue 6 https://doi.org/10.1088/0741-3335/48/6/009	journal	May 2006
Upgraded flowing liquid lithium limiter for improving Li coverage uniformity and erosion resistance in EAST device Zuo, G. Z.; Hu, J. S.; Maingi, R. Review of Scientific Instruments, Vol. 88, Issue 12 https://doi.org/10.1063/1.4997806	journal	December 2017
Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices Ruzic, D. N.; Xu, W.; Andruczyk, D. Nuclear Fusion, Vol. 51, Issue 10 https://doi.org/10.1088/0029-5515/51/10/102002	journal	August 2011
Impact of lithium-coated walls on plasma performance in the TJ-II stellarator Sánchez, J.; Tabarés, F. L.; Tafalla, D. Journal of Nuclear Materials, Vol. 390-391 https://doi.org/10.1016/j.jnucmat.2009.01.224	journal	June 2009
First results of lithium experiments on EAST and HT-7 Zuo, G. Z.; Hu, J. S.; Li, J. G. Journal of Nuclear Materials, Vol. 415, Issue 1 https://doi.org/10.1016/j.jnucmat.2010.08.052	journal	August 2011
Edge properties with the liquid lithium limiter in FTU—experiment and transport modelling Pericoli-Ridolfini, V.; Apicella, M. L.; Mazzitelli, G. Plasma Physics and Controlled Fusion, Vol. 49, Issue 7 https://doi.org/10.1088/0741-3335/49/7/S09	journal	June 2007
Conference Report on the 3rd International Symposium on Lithium Application for Fusion Devices Mazzitelli, G.; Hirooka, Y.; Hu, J. S. Nuclear Fusion, Vol. 55, Issue 2 https://doi.org/10.1088/0029-5515/55/2/027001	journal	January 2015
Liquid lithium surface control and its effect on plasma performance in the HT-7 tokamak Zuo, G. Z.; Ren, J.; Hu, J. S. Fusion Engineering and Design, Vol. 89, Issue 12 https://doi.org/10.1016/j.fusengdes.2014.05.020	journal	December 2014
Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak Majeski, R.; Doerner, R.; Gray, T. Physical Review Letters, Vol. 97, Issue 7 https://doi.org/10.1103/PhysRevLett.97.075002	journal	August 2006
Lithium erosion experiments and modelling under quiescent plasma conditions in DIII-D Allain, J. P.; Whyte, D. G.; Brooks, J. N. Nuclear Fusion, Vol. 44, Issue 5 https://doi.org/10.1088/0029-5515/44/5/009	journal	April 2004
Liquid lithium divertor system for fusion reactor Nagayama, Yoshio Fusion Engineering and Design, Vol. 84, Issue 7-11 https://doi.org/10.1016/j.fusengdes.2009.02.002	journal	June 2009
Overview of the FTU results Pericoli-Ridolfini, V.; Alekseyev, A.; Angelini, B. Nuclear Fusion, Vol. 47, Issue 10 https://doi.org/10.1088/0029-5515/47/10/S10	journal	September 2007
Review of FTU results with the liquid lithium limiter Mazzitelli, G.; Apicella, M. L.; Ridolfini, V. Pericoli Fusion Engineering and Design, Vol. 85, Issue 6 https://doi.org/10.1016/j.fusengdes.2010.08.038	journal	November 2010
Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST Zuo, G. Z.; Hu, J. S.; Maingi, R. Nuclear Fusion, Vol. 59, Issue 1 https://doi.org/10.1088/1741-4326/aaedcb	journal	November 2018
The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus Experiment Maingi, R.; Boyle, D. P.; Canik, J. M. Nuclear Fusion, Vol. 52, Issue 8 https://doi.org/10.1088/0029-5515/52/8/083001	journal	June 2012