A review of lithium application for the plasma-facing material in EAST Tokamak

被引：3

作者：

Hu, J. S. ^{[1
,2
]}

Li, L. ^{[1
]}

Zuo, G. Z. ^{[1
]}

Sun, Z. ^{[3
]}

Xu, W. ^{[1
,4
]}

Meng, X. C. ^{[1
,4
]}

Li, C. L. ^{[1
,4
]}

Tang, Z. L. ^{[1
]}

Sun, J. Z. ^{[5
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, HFIPS, Hefei 230031, Anhui, Peoples R China

[2] CAS Key Lab Photovolta & Energy Conservat Mat, Hefei 230031, Anhui, Peoples R China

[3] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

[4] Inst Energy, Hefei Comprehens Natl Sci Ctr, Hefei 230026, Anhui, Peoples R China

[5] Dalian Univ Technol, Sch Phys & Optoelect Technol, Dalian 116024, Liaoning, Peoples R China

来源：

REVIEWS OF MODERN PLASMA PHYSICS | 2023年 / 7卷 / 01期

关键词：

Lithium; Plasma-facing material; Tokamak; EAST; STIMULATED RAMAN-SCATTERING; FINITE-BANDWIDTH DRIVER; SPACE-TIME FLUCTUATIONS; PARAMETRIC-INSTABILITIES; TEMPERATURE; IGNITION; LASERS; BACKSCATTER; GENERATION; INTENSITY;

D O I：

10.1007/s41614-023-00114-7

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

As a low-Z material, lithium is widely tested and used in tokamak devices for particle recycling and impurity control to improve plasma performance. Lithium application as plasma-facing materials via different methods, such as coating, injection and flowing liquid limiter, has been investigated more than 10 years on EAST. This paper presents the development of the lithium techniques applied on EAST, and reviews the progresses on the investigation of its interaction with plasma and its effects on the improvement on the plasma performances. In addition, this paper further discusses the potential applications of lithium technique in future fusion devices.

引用

页数：53

共 50 条

[1] BERYLLIUM - A BETTER TOKAMAK PLASMA-FACING MATERIAL
WILSON, KL
CAUSEY, RA
HSU, WL
MILLS, BE
SMITH, MF
WHITLEY, JB
[J]. JOURNAL OF VACUUM SCIENCE & TECHNOLOGY A-VACUUM SURFACES AND FILMS, 1990, 8 (03): : 1750 - 1759
[2] Hydrogen and vacancies in the tokamak plasma-facing material beryllium
Krimmel, H
Fahnle, M
[J]. JOURNAL OF NUCLEAR MATERIALS, 1998, 255 (01) : 72 - 74
[3] Properties of hydrogen isotopes in the tokamak plasma-facing material beryllium
Krimmel, H
Fahnle, M
[J]. JOURNAL OF NUCLEAR MATERIALS, 1996, 231 (1-2) : 159 - 161
[4] Plasma-facing components damage and its effects on plasma performance in EAST tokamak
Gao, Binfu
Ding, Rui
Xie, Hai
Zeng, Long
Zhang, Ling
Wang, Baoguo
Li, Changjun
Zhu, Dahuan
Yan, Rong
Chen, Junling
[J]. FUSION ENGINEERING AND DESIGN, 2020, 156
[5] Plasma-Facing Components of the TRT Tokamak
I. V. Mazul
R. N. Giniyatulin
A. A. Kavin
N. V. Litunovskii
A. N. Makhankov
P. Yu. Piskarev
V. N. Tanchuk
[J]. Plasma Physics Reports, 2021, 47 : 1220 - 1237
[6] Plasma-Facing Components of the TRT Tokamak
Mazul, I., V
Giniyatulin, R. N.
Kavin, A. A.
Litunovskii, N., V
Makhankov, A. N.
Piskarev, P. Yu
Tanchuk, V. N.
[J]. PLASMA PHYSICS REPORTS, 2021, 47 (12) : 1220 - 1237
[7] Compatibility of lithium plasma-facing surfaces with high edge temperatures in the Lithium Tokamak Experiment
Majeski, R.
Bell, R. E.
Boyle, D. P.
Kaita, R.
Kozub, T.
LeBlanc, B. P.
Lucia, M.
Maingi, R.
Merino, E.
Raitses, Y.
Schmitt, J. C.
Allain, J. P.
Bedoya, F.
Bialek, J.
Biewer, T. M.
Canik, J. M.
Buzi, L.
Koel, B. E.
Patino, M. I.
Capece, A. M.
Hansen, C.
Jarboe, T.
Kubota, S.
Peebles, W. A.
Tritz, K.
[J]. PHYSICS OF PLASMAS, 2017, 24 (05)
[8] Erosion of Be as plasma-facing material
Roth, J
Eckstein, W
Guseva, M
[J]. FUSION ENGINEERING AND DESIGN, 1997, 37 (04) : 465 - 480
[9] Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor
Whyte, DG
Evans, TE
Wong, CPC
West, WP
Bastasz, R
Allain, JP
Brooks, JN
[J]. FUSION ENGINEERING AND DESIGN, 2004, 72 (1-3) : 133 - 147
[10] Hydrogen in tungsten as plasma-facing material
Roth, Joachim
Schmid, Klaus
[J]. PHYSICA SCRIPTA, 2011, T145

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