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 in | Chinese physics B Vol. 23; no. 11; pp. 403 - 409 |
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| Main Author | |
| Format | Journal Article |
| Language | English |
| Published |
01.11.2014
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| Subjects | |
| Online Access | Get full text |
| ISSN | 1674-1056 2058-3834 1741-4199 |
| DOI | 10.1088/1674-1056/23/11/115201 |
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| Abstract | 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. |
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| AbstractList | 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. 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. |
| Author | 桑超峰 戴舒宇 孙继忠 Bonnin Xavier 徐倩 丁芳 王德真 |
| AuthorAffiliation | 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 LSPM-CNRS, Universite Paris 13, Sorbonne Paris Cite, Villetaneuse 93430, France lnstitute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China |
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| CitedBy_id | crossref_primary_10_1088_1674_1056_ab8204 crossref_primary_10_7498_aps_66_084102 crossref_primary_10_1016_j_fusengdes_2016_02_104 |
| Cites_doi | 10.1016/j.jnucmat.2007.04.007 10.1088/0741-3335/52/7/075007 10.1088/0029-5515/41/12/218 10.1016/j.fusengdes.2008.11.049 10.1088/0741-3335/53/11/115004 10.1063/1.1880013 10.1016/j.jnucmat.2011.01.007 10.13182/FST05-A991 10.1016/j.fusengdes.2012.02.028 10.1016/j.fusengdes.2010.03.068 10.1016/j.jnucmat.2013.01.249 10.1016/j.jnucmat.2009.01.097 10.1016/j.jnucmat.2013.01.019 10.1016/j.jnucmat.2008.09.008 10.1088/0741-3335/38/2/001 10.1016/j.fusengdes.2014.01.040 10.1088/0029-5515/52/4/043003 10.7498/aps.63.035204 10.1088/0741-3335/55/2/025006 10.1088/0741-3335/52/4/042001 10.1002/ctpp.200810048 10.1116/1.1492699 10.7498/aps.62.245206 10.1016/j.fusengdes.2008.05.011 10.1016/S0022-3115(01)00732-2 10.1016/j.jnucmat.2007.04.029 10.1016/j.jnucmat.2009.01.216 10.1002/ctpp.200710072 10.1016/S0022-3115(02)01375-2 10.1016/j.jnucmat.2009.01.136 10.1063/1.1768174 10.1016/j.fusengdes.2010.06.026 10.1088/0029-5515/39/2/410 |
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| DocumentTitleAlternate | Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps |
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| Notes | 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 |
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| References | 22 23 25 26 Skinner C H (7) 1999; 39 27 28 Komm M (18) 2011; 53 31 Du H L (1) 2013; 62 33 12 35 14 15 16 Sang C (13) 2012; 52 Huang Y (2) 2014; 63 19 Ding F (24) 2014 Tanabe T (32) 2005; 48 Sang C (17) 2010; 52 Zohm H (29) 1996; 38 3 4 Stangeby P C (34) 2000 5 6 8 Komm M (11) 2013; 55 Federici G (30) 2001; 41 9 20 Matveev D (10) 2010; 52 21 |
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| SubjectTerms | 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 |
| Title | Effects of some parameters on the divertor plasma sheath characteristics and fuel retention in castellated tungsten tile gaps |
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