面临大等离子体热负荷的钨点的模拟温度

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
J. Moritz , S. Heuraux , M. Lesur , E. Gravier , F. Brochard , L. Marot , P. Hiret
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引用次数: 0

摘要

在热核聚变实验堆这样的聚变装置中,等离子体与第一壁之间的相互作用是一个重大问题,因为冲击第一壁的热通量很高,通常达到几十兆瓦/平方米。这些高热流量会导致在面向等离子体的部件上形成热点,例如在分流器板和天线中使用的钨。这将导致材料侵蚀和等离子体核心污染。我们的研究利用流体建模和粒子内胞(PIC)模拟研究了钨表面在这些条件下的热行为。我们研究了热电子发射对鞘势和热传递的影响。模拟结果表明,热电子发射会降低鞘电压,同时由于电子增强了热通量而提高了表面温度。此外,我们还探讨了光斑尺寸(S)与周围表面长度(Ly)之比对表面温度的影响。我们发现,较高的 Ly/S 比值可使表面在系统进入空间电荷受限状态之前达到更高的温度,在该状态下,热离子电流达到最大值,并大大高于整个表面都发射的情况(Ly=S)。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Simulated temperature of a tungsten spot facing large plasma heat loads
In fusion devices like ITER, plasma-wall interactions are a significant concern due to the high heat fluxes, often tens of MW/m2, impacting the first wall. These intense heat fluxes can lead to the formation of hot spots on components facing the plasma, such as tungsten, used in divertor plates and antennas. This results in material erosion and plasma core contamination. Our study investigates the thermal behavior of tungsten surfaces under these conditions using fluid modeling and Particle-In-Cell (PIC) simulations. We examine the effects of thermionic electron emission on the sheath potential and heat transmission. The simulations reveal that thermionic emission can decrease the sheath voltage, increasing the surface temperature due to enhanced heat flux due to electrons. Additionally, we explore how the ratio between the spot size (S) and the surrounding surface length (Ly) influences the surface temperature. We find that a higher Ly/S ratio allows the surface to reach higher temperatures before the system enters the space-charge-limited regime, where thermionic current is maximized and considerably larger than the case where the entire surface is emissive (Ly=S).
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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