Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST
Abstract
Significant engineering and physic progress was made by the upgrade of a flowing liquid lithium limiter (FLiLi) inserted into EAST H-mode discharges in 2016. The progress includes an improvement of liquid Li coverage uniformity, no macroscopic surface erosion by plasma materials interaction, effective removal of 55% of the discharge heat flux using high pressure He cooling during ohmic discharges, and the demonstrated ability to restart Li flow for a second experiment performed a week after the first. With increasing Li flow rate, fuel particle recycling and Fe impurity radiation gradually decreased, and plasma performance slightly improved, but there was no impact on the edge tungsten influx. No obvious Li bursts appeared during operation with up to about 4.5 MW auxiliary heating power with peak heat flux reaching ~4 MW m–2 on FLiLi. In addition, a gradual mitigation of edge localized mode (ELM) activity was observed with FLiLi operation. Lastly, short-lived ELM-free phases were observed for the first time in EAST during FLiLi insertion, with increasing τ E and transient H98(y, 2) < 2.
- Authors:
-
more »
- Chinese Academy of Sciences, Anhui (China)
- Chinese Academy of Sciences, Anhui (China); CAS key Laboratory of Photovoltaic and Energy Conservation Materials, Hefei (China)
- Princeton Univ., Princeton, NJ (United States)
- Chinese Academy of Sciences, Anhui (China); Princeton Univ., Princeton, NJ (United States)
- Chinese Academy of Sciences, Anhui (China); Shenzhen Univ., Shenzhen (China)
- Hefei Univ. of Technology, Hefei (China)
- Johns Hopkins Univ., Baltimore, MD (United States)
- Univ. of Chinese Academy of Sciences, Beijing (China)
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE
- Contributing Org.:
- EAST team
- OSTI Identifier:
- 1512785
- Grant/Contract Number:
- 2017YFA0402500; 2017YFE0301100; 2017YFE0301300; AC02-09CH11466; 11775261; 11625524; 11605246; 11075185; 1102156
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nuclear Fusion
- Additional Journal Information:
- Journal Volume: 59; Journal Issue: 1; Journal ID: ISSN 0029-5515
- Publisher:
- IOP Science
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; liquid Li; Li uniformity; heat flux; high power plasma; edge localized mode
Citation Formats
Zuo, G. Z., Hu, J. S., Maingi, R., Sun, Z., Yang, Q. X., Huang, M., Meng, X. C., Xu, W., Qian, Y. Z., Li, C. L., Bi, H. L., Chen, Y., Yuan, X. L., Han, X. F., Zhu, X., Wang, Y. F., Zhang, L., Liu, H. Q., Wang, L., Gong, X. Z., Tritz, K., Diallo, A., Lunsford, R., Ni, M. J., and Li, J. G. Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST. United States: N. p., 2018.
Web. doi:10.1088/1741-4326/aaedcb.
Zuo, G. Z., Hu, J. S., Maingi, R., Sun, Z., Yang, Q. X., Huang, M., Meng, X. C., Xu, W., Qian, Y. Z., Li, C. L., Bi, H. L., Chen, Y., Yuan, X. L., Han, X. F., Zhu, X., Wang, Y. F., Zhang, L., Liu, H. Q., Wang, L., Gong, X. Z., Tritz, K., Diallo, A., Lunsford, R., Ni, M. J., & Li, J. G. Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST. United States. https://doi.org/10.1088/1741-4326/aaedcb
Zuo, G. Z., Hu, J. S., Maingi, R., Sun, Z., Yang, Q. X., Huang, M., Meng, X. C., Xu, W., Qian, Y. Z., Li, C. L., Bi, H. L., Chen, Y., Yuan, X. L., Han, X. F., Zhu, X., Wang, Y. F., Zhang, L., Liu, H. Q., Wang, L., Gong, X. Z., Tritz, K., Diallo, A., Lunsford, R., Ni, M. J., and Li, J. G. Tue .
"Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST". United States. https://doi.org/10.1088/1741-4326/aaedcb. https://www.osti.gov/servlets/purl/1512785.
@article{osti_1512785,
title = {Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST},
author = {Zuo, G. Z. and Hu, J. S. and Maingi, R. and Sun, Z. and Yang, Q. X. and Huang, M. and Meng, X. C. and Xu, W. and Qian, Y. Z. and Li, C. L. and Bi, H. L. and Chen, Y. and Yuan, X. L. and Han, X. F. and Zhu, X. and Wang, Y. F. and Zhang, L. and Liu, H. Q. and Wang, L. and Gong, X. Z. and Tritz, K. and Diallo, A. and Lunsford, R. and Ni, M. J. and Li, J. G.},
abstractNote = {Significant engineering and physic progress was made by the upgrade of a flowing liquid lithium limiter (FLiLi) inserted into EAST H-mode discharges in 2016. The progress includes an improvement of liquid Li coverage uniformity, no macroscopic surface erosion by plasma materials interaction, effective removal of 55% of the discharge heat flux using high pressure He cooling during ohmic discharges, and the demonstrated ability to restart Li flow for a second experiment performed a week after the first. With increasing Li flow rate, fuel particle recycling and Fe impurity radiation gradually decreased, and plasma performance slightly improved, but there was no impact on the edge tungsten influx. No obvious Li bursts appeared during operation with up to about 4.5 MW auxiliary heating power with peak heat flux reaching ~4 MW m–2 on FLiLi. In addition, a gradual mitigation of edge localized mode (ELM) activity was observed with FLiLi operation. Lastly, short-lived ELM-free phases were observed for the first time in EAST during FLiLi insertion, with increasing τ E and transient H98(y, 2) < 2.},
doi = {10.1088/1741-4326/aaedcb},
journal = {Nuclear Fusion},
number = 1,
volume = 59,
place = {United States},
year = {Tue Nov 27 00:00:00 EST 2018},
month = {Tue Nov 27 00:00:00 EST 2018}
}
Web of Science
Works referenced in this record:
On the physics guidelines for a tokamak DEMO
journal, June 2013
- Zohm, H.; Angioni, C.; Fable, E.
- Nuclear Fusion, Vol. 53, Issue 7
Actively convected liquid metal divertor
journal, October 2014
- Shimada, Michiya; Hirooka, Yoshi
- Nuclear Fusion, Vol. 54, Issue 12
Overview of the physics and engineering design of NSTX upgrade
journal, July 2012
- Menard, J. E.; Gerhardt, S.; Bell, M.
- Nuclear Fusion, Vol. 52, Issue 8
A simulation study of large power handling in the divertor for a Demo reactor
journal, November 2013
- Asakura, Nobuyuki; Shimizu, Katsuhiro; Hoshino, Kazuo
- Nuclear Fusion, Vol. 53, Issue 12
Liquid lithium divertor system for fusion reactor
journal, June 2009
- Nagayama, Yoshio
- Fusion Engineering and Design, Vol. 84, Issue 7-11
Conference Report on the 4rd International Symposium on Lithium Applications
journal, September 2016
- Tabares, F. L.; Hirooka, Y.; Maingi, R.
- Nuclear Fusion, Vol. 56, Issue 12
Conference Report on the 3rd International Symposium on Lithium Application for Fusion Devices
journal, January 2015
- Mazzitelli, G.; Hirooka, Y.; Hu, J. S.
- Nuclear Fusion, Vol. 55, Issue 2
Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak
journal, August 2006
- Majeski, R.; Doerner, R.; Gray, T.
- Physical Review Letters, Vol. 97, Issue 7
Effects of large area liquid lithium limiters on spherical torus plasmas
journal, March 2005
- Kaita, R.; Majeski, R.; Boaz, M.
- Journal of Nuclear Materials, Vol. 337-339
Performance projections for the lithium tokamak experiment (LTX)
journal, April 2009
- Majeski, R.; Berzak, L.; Gray, T.
- Nuclear Fusion, Vol. 49, Issue 5
Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment
journal, May 2017
- Majeski, R.; Bell, R. E.; Boyle, D. P.
- Physics of Plasmas, Vol. 24, Issue 5
Observation of Flat Electron Temperature Profiles in the Lithium Tokamak Experiment
journal, July 2017
- Boyle, D. P.; Majeski, R.; Schmitt, J. C.
- Physical Review Letters, Vol. 119, Issue 1
Impact of lithium-coated walls on plasma performance in the TJ-II stellarator
journal, June 2009
- Sánchez, J.; Tabarés, F. L.; Tafalla, D.
- Journal of Nuclear Materials, Vol. 390-391
Overview of the FTU results
journal, September 2007
- Pericoli-Ridolfini, V.; Alekseyev, A.; Angelini, B.
- Nuclear Fusion, Vol. 47, Issue 10
Edge properties with the liquid lithium limiter in FTU—experiment and transport modelling
journal, June 2007
- Pericoli-Ridolfini, V.; Apicella, M. L.; Mazzitelli, G.
- Plasma Physics and Controlled Fusion, Vol. 49, Issue 7
Review of FTU results with the liquid lithium limiter
journal, November 2010
- Mazzitelli, G.; Apicella, M. L.; Ridolfini, V. Pericoli
- Fusion Engineering and Design, Vol. 85, Issue 6
Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices
journal, May 2006
- Mirnov, S. V.; Azizov, E. A.; Evtikhin, V. A.
- Plasma Physics and Controlled Fusion, Vol. 48, Issue 6
An overview of lithium experiments on HT-7 and EAST during 2012
journal, December 2014
- Hu, J. S.; Ren, J.; Sun, Z.
- Fusion Engineering and Design, Vol. 89, Issue 12
First results of lithium experiments on EAST and HT-7
journal, August 2011
- Zuo, G. Z.; Hu, J. S.; Li, J. G.
- Journal of Nuclear Materials, Vol. 415, Issue 1
Overview of TJ-II experiments
journal, August 2011
- Sánchez, J.; Acedo, M.; Alegre, D.
- Nuclear Fusion, Vol. 51, Issue 9
The effect of progressively increasing lithium coatings on plasma discharge characteristics, transport, edge profiles and ELM stability in the National Spherical Torus Experiment
journal, June 2012
- Maingi, R.; Boyle, D. P.; Canik, J. M.
- Nuclear Fusion, Vol. 52, Issue 8
Enhanced H-mode pedestals with lithium injection in DIII-D
journal, May 2015
- Osborne, T. H.; Jackson, G. L.; Yan, Z.
- Nuclear Fusion, Vol. 55, Issue 6
New Steady-State Quiescent High-Confinement Plasma in an Experimental Advanced Superconducting Tokamak
journal, February 2015
- Hu, J. S.; Sun, Z.; Guo, H. Y.
- Physical Review Letters, Vol. 114, Issue 5
ELM elimination with Li powder injection in EAST discharges using the tungsten upper divertor
journal, January 2018
- Maingi, R.; Hu, J. S.; Sun, Z.
- Nuclear Fusion, Vol. 58, Issue 2
High frequency pacing of edge localized modes by injection of lithium granules in DIII-D H-mode discharges
journal, April 2016
- Bortolon, A.; Maingi, R.; Mansfield, D. K.
- Nuclear Fusion, Vol. 56, Issue 5
Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas
journal, July 2013
- Jaworski, M. A.; Abrams, T.; Allain, J. P.
- Nuclear Fusion, Vol. 53, Issue 8
Active radiative liquid lithium divertor concept
journal, December 2014
- Ono, M.; Jaworski, M. A.; Kaita, R.
- Fusion Engineering and Design, Vol. 89, Issue 12
Latest Results From the Hybrid Illinois Device for Research and Applications (HIDRA)
journal, July 2018
- Rizkallah, R.; Andruczyk, D.; Shone, A.
- IEEE Transactions on Plasma Science, Vol. 46, Issue 7
A flowing liquid lithium limiter for the Experimental Advanced Superconducting Tokamak
journal, February 2015
- Ren, J.; Zuo, G. Z.; Hu, J. S.
- Review of Scientific Instruments, Vol. 86, Issue 2
Molecular dynamics simulation of wetting behaviors of Li on W surfaces
journal, April 2017
- Sun, Xuegui; Xiao, Shifang; Deng, Huiqiu
- Fusion Engineering and Design, Vol. 117
Upgraded flowing liquid lithium limiter for improving Li coverage uniformity and erosion resistance in EAST device
journal, December 2017
- Zuo, G. Z.; Hu, J. S.; Maingi, R.
- Review of Scientific Instruments, Vol. 88, Issue 12
Application of lithium in systems of fusion reactors. 1. Physical and chemical properties of lithium
journal, March 2009
- Lyublinski, I. E.; Vertkov, A. V.; Evtikhin, V. A.
- Plasma Devices and Operations, Vol. 17, Issue 1
Collisional and thermal effects on liquid lithium sputtering
journal, November 2007
- Allain, J. P.; Coventry, M. D.; Ruzic, D. N.
- Physical Review B, Vol. 76, Issue 20
Modelling of lithium erosion and transport in FTU lithium experiments
journal, July 2013
- Ding, R.; Maddaluno, G.; Apicella, M. L.
- Journal of Nuclear Materials, Vol. 438
Macroscopic motion of liquid metal plasma facing components in a diverted plasma
journal, August 2011
- Jaworski, M. A.; Gerhardt, S. P.; Morley, N. B.
- Journal of Nuclear Materials, Vol. 415, Issue 1
Liquid lithium surface control and its effect on plasma performance in the HT-7 tokamak
journal, December 2014
- Zuo, G. Z.; Ren, J.; Hu, J. S.
- Fusion Engineering and Design, Vol. 89, Issue 12
Density profile evolution on EAST tokamak by the polarimeter/interferometer system
journal, June 2018
- Zhu, X.; Zeng, L.; Liu, H. Q.
- Fusion Engineering and Design, Vol. 131
Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices
journal, August 2011
- Ruzic, D. N.; Xu, W.; Andruczyk, D.
- Nuclear Fusion, Vol. 51, Issue 10
Overview of the FTU results
journal, October 2005
- Angelini, B.; Annibaldi, S. V.; Apicella, M. L.
- Nuclear Fusion, Vol. 45, Issue 10
Overview of TJ-II experiments
conference, January 2006
- López-Bruna, D.
- PLASMA AND FUSION SCIENCE: 16th IAEA Technical Meeting on Research using Small Fusion Devices; XI Latin American Workshop on Plasma Physics, AIP Conference Proceedings
Overview of the FTU results
journal, September 2009
- Tuccillo, A. A.; Alekseyev, A.; Angelini, B.
- Nuclear Fusion, Vol. 49, Issue 10
Overview of TJ-II experiments
journal, September 2007
- Sánchez, J.; Acedo, M.; Alonso, A.
- Nuclear Fusion, Vol. 47, Issue 10
Works referencing / citing this record:
Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility
journal, July 2019
- Wallace, G. M.; Kessel, C. E.; Hosea, J.
- Fusion Science and Technology, Vol. 76, Issue 1