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

J. S. Hu; L. Li; G. Z. Zuo; Z. Sun; W. Xu; X. C. Meng; C. L. Li; Z. L. Tang; J. Z. Sun

doi:10.1007/s41614-023-00114-7

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

J. S. Hu, L. Li, G. Z. Zuo, Z. Sun, W. Xu, X. C. Meng, C. L. Li, Z. L. Tang, J. Z. Sun

PPPL Tokamak Expermntl Science

Research output: Contribution to journal › Article › peer-review

10 Scopus citations

Abstract

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.

Original language	English (US)
Article number	9
Journal	Reviews of Modern Plasma Physics
Volume	7
Issue number	1
DOIs	https://doi.org/10.1007/s41614-023-00114-7
State	Published - Dec 2023

All Science Journal Classification (ASJC) codes

Condensed Matter Physics
Physics and Astronomy (miscellaneous)

Keywords

EAST
Lithium
Plasma-facing material
Tokamak

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10.1007/s41614-023-00114-7

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title = "A review of lithium application for the plasma-facing material in EAST Tokamak",

abstract = "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.",

keywords = "EAST, Lithium, Plasma-facing material, Tokamak",

author = "Hu, \{J. S.\} and L. Li and Zuo, \{G. Z.\} and Z. Sun and W. Xu and Meng, \{X. C.\} and Li, \{C. L.\} and Tang, \{Z. L.\} and Sun, \{J. Z.\}",

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month = dec,

doi = "10.1007/s41614-023-00114-7",

language = "English (US)",

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T1 - A review of lithium application for the plasma-facing material in EAST Tokamak

AU - Hu, J. S.

AU - Li, L.

AU - Zuo, G. Z.

AU - Sun, Z.

AU - Xu, W.

AU - Meng, X. C.

AU - Li, C. L.

AU - Tang, Z. L.

AU - Sun, J. Z.

PY - 2023/12

Y1 - 2023/12

N2 - 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.

AB - 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.

KW - EAST

KW - Lithium

KW - Plasma-facing material

KW - Tokamak

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

Abstract

All Science Journal Classification (ASJC) codes

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