Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps

Castellation of plasma facing components is foreseen as the best solution for ensuring the lifetime of future fusion devices. However, the gaps between the resulting surface elements can increase fuel retention and complicate fuel removal issues. To know how the fuel is retained inside the gaps, the...

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Published inChinese physics B Vol. 23; no. 11; pp. 403 - 409
Main Author 桑超峰 戴舒宇 孙继忠 Bonnin Xavier 徐倩 丁芳 王德真
Format Journal Article
LanguageEnglish
Published 01.11.2014
Subjects
Fuels
Inclination angle
Magnetic fields
Mathematical models
Penetration depth
Plasma (physics)
Plasma sheaths
Plasma temperature
Tungsten
偏滤器
动力学模型
效果参数
燃料
瓷砖
穿透深度
等离子体鞘
缝隙
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ISSN1674-1056
2058-3834
1741-4199
DOI10.1088/1674-1056/23/11/115201

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Summary:Castellation of plasma facing components is foreseen as the best solution for ensuring the lifetime of future fusion devices. However, the gaps between the resulting surface elements can increase fuel retention and complicate fuel removal issues. To know how the fuel is retained inside the gaps, the plasma sheath around the gaps needs to be understood first. In this work, a kinetic model is used to study plasma characteristics around the divertor gaps with the focus on the H＋ penetration depth inside the poloidal gaps, and a rate-theory model is coupled to simulate the hydrogen retention inside the tungsten gaps. By varying the magnetic field strength and plasma temperature, we find that the H＋ cyclotron radius has a significant effect on the penetration depth. Besides, the increase of magnetic field inclination angle can also increase the penetration depth. It is found in this work that parameters as well as the penetration depth strongly affect fuel retention in tungsten gaps.
Bibliography:Sang Chao-Feng, Dai Shu-Yu, Sun Ji-Zhong, Bonnin Xavier, Xu Qian, Ding Fang, and Wang De-Zhen（ a） Key Laboratory of Materials Modification by Laser, Ion and Electron Beams （Ministry of Education）, School of Physics and Optoelectronic Engineering, Dalian University of Technology, Dalian 116024, China b ） LSPM-CNRS, Universit6 Paris 13, Sorbonne Paris Cit6, Villetaneuse 93430, Prance C） Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China
Castellation of plasma facing components is foreseen as the best solution for ensuring the lifetime of future fusion devices. However, the gaps between the resulting surface elements can increase fuel retention and complicate fuel removal issues. To know how the fuel is retained inside the gaps, the plasma sheath around the gaps needs to be understood first. In this work, a kinetic model is used to study plasma characteristics around the divertor gaps with the focus on the H＋ penetration depth inside the poloidal gaps, and a rate-theory model is coupled to simulate the hydrogen retention inside the tungsten gaps. By varying the magnetic field strength and plasma temperature, we find that the H＋ cyclotron radius has a significant effect on the penetration depth. Besides, the increase of magnetic field inclination angle can also increase the penetration depth. It is found in this work that parameters as well as the penetration depth strongly affect fuel retention in tungsten gaps.
divertor gaps, penetration depth, plasma sheath, fuel retention
11-5639/O4
ObjectType-Article-1
SourceType-Scholarly Journals-1
ObjectType-Feature-2
content type line 23
ISSN:1674-1056
2058-3834
1741-4199
DOI:10.1088/1674-1056/23/11/115201