DIII-D托卡马克中Dimes碳消融棒的设计与测试
Design and Testing of Dimes Carbon Ablation Rods in the DIII-D Tokamak
AI总结：
本研究针对高速航天器碳基隔热罩消融模型测试需求，设计了适用于DIII-D托卡马克偏滤器高热流环境的多种构型ATJ石墨棒，分析了SiC涂层方案，并介绍了初步实验结果。
摘要：
我们介绍了为DIII-D托卡马克（一种磁等离子体约束装置）[1]下偏滤器中高热流（最高50 MW/m²）下的消融实验开发的ATJ石墨棒的设计。开展这项工作的动机是需要测试与高速航天器大气再入所用碳基隔热罩相关的消融模型，这类场景中遇到的热流可与DIII-D偏滤器等离子体中达到的热流相当。我们分析了棒材迎流面的几种不同设计，包括“尖头型”“钝头型”和“凹面型”。研究最后一种形状是因为它有望通过俘获中性粒子的增强辐射和降低的平行等离子体压力来降低棒材表面的热流。我们还分析了在数根碳消融棒的暴露部分涂覆一层薄（约30微米）碳化硅（SiC）的可能性，用以基准验证其侵蚀计算和寿命预测。这类计算颇具研究价值，因为SiC是热防护系统（TPS）和聚变等离子体面向材料（PFM）的一种有前景的材料。本文还讨论了DIII-D棒材消融实验的初步结果。
英文摘要：
We present the design of ATJ graphite rods developed for ablation experiments under high heat flux (up to 50 MW/m2) in the lower divertor of the DIII-D tokamak [1], a magnetic plasma confinement device. This work is motivated by the need to test ablation models relevant to carbon-based thermal shields used in high-speed spacecraft atmospheric entries, where the heat fluxes encountered can be comparable to those achieved in the DIII-D divertor plasma. Several different designs for the flow-facing side of the rod are analyzed, including "sharp nose," "blunt," and "concave". The last shape is studied for its potential to lower heat fluxes at the rod surface by increased radiation from trapped neutrals and reduced parallel plasma pressure. We also analyze the possibility of applying a thin (approximately 30 microns) layer of silicon carbide (SiC) to the exposed part of several carbon ablation rods to benchmark its erosion calculations and lifetime predictions. Such calculations are of interest as SiC represents a promising material for both thermal protection systems (TPS) and a fusion plasma-facing material (PFM). Preliminary results from the DIII-D rod ablation experiments are also discussed.
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