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

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Chinese Physics B 2014年第11期23卷 403-409页

作者：桑超峰戴舒宇孙继忠 Bonnin Xavier 徐倩丁芳王德真 Key Laboratory of Materials Modification by Laser Ion and Electron Beams (Ministry of Education)School of Physics and Optoelectronic Engineering Dalian University of Technology LSPM-CNRS Universit Paris 13 Sorbonne Paris Cit Villetaneuse 93430 France Institute of Plasma Physics Chinese Academy of Sciences

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.

关键词： divertor gaps penetration depth plasma sheath fuel retention

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Temporal and spatial evolution measurement of laser-induced breakdown spectroscopy on hydrogen retention in tantalum

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Plasma Science and Technology 2020年第7期22卷 59-64页

作者： Cong LI Jiajia YOU Huace WU Ding WU Liying SUN Jiamin LIU Qianhui LI Ran HAI Xingwei WU Hongbin DING Key Laboratory of Materials Modification by Laser Ion and Electron Beams(Ministry of Education)School of PhysicsDalian University of TechnologyDalian 116024People's Republic of China

fuel retention measurement on plasma-facing components is an active field of study in magnetic confinement nuclear fusion *** laser-induced breakdown spectroscopy(LIBS)diagnostic method has been well demonstrated to detect the elemental distribution in *** this work,an upgraded co-axis LIBS system based on a linear fiber bundle collection system has been developed to measure the hydrogen(H) retention on a tantalum(Ta) sample under a vacuum *** spatial resolution measurement of the different positions of the LIBS plasma can be achieved simultaneously with varying delay *** temporal and spatial evolution results of LIBS plasma emission show that the H plasma observably expands from the delay times of 0-200 *** diameter of Ta plasma is about 6 mm which is much less than the size of H plasma after 200 *** difference in the temporal and spatial evolution behaviors between H plasma and Ta plasma is due to the great difference in the atomic mass of H and *** depth profile result shows that H retention mainly exists on the surface of the *** temporal and spatial evolution behaviors of the electron excited temperature are consistent with that of the Ta *** result will further improve the understanding of the evolution of the dynamics of LIBS plasma and optimize the current collection system of in situ LIBS in fusion devices.

关键词： temporal and spatial evolution fuel retention tokamak laser-induced breakdown spectroscopy

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