DIII-D高级导流器低温泵氦板验证试验

C. Baxi, G.J. Loughon, A. Langhorn, K. Schaubel, J.P. Smith, A. M. Gootgeld, G. Campbell, M. Menon
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引用次数: 1

摘要

计划在DIII-D托卡马克的下部导流器部分安装一个低温泵,泵速为50000 l/s,排气量为2670 Pa-l/s (20 torr-l/s)。该低温泵的氦面板采用了同轴逆流结构。评估了该配置的冷却速率和流体稳定性。进行了原型试验以增加对设计的信心。氦板的冷却速率与分析预测相当一致,在可接受的范围内。结果表明,设计流量稳定,两相压降预测精度较高。结果证实,在等离子体喷射之间的几分钟内,氦板可以从300 K冷却到液氦温度。氦气流动结果表明,当设计流量为5 g/s时,热负荷达到54 W时,氦气流动是稳定的。氦气板运行时的预期热负荷约为10w。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Verification test for helium panel of cryopump for DIII-D advanced divertor
It is planned to install a cryogenic pump, in the lower divertor portion of the DIII-D tokamak with a pumping speed of 50000 l/s and an exhaust of 2670 Pa-l/s (20 torr-l/s). A coaxial counterflow configuration has been chosen for the helium panel of this cryogenic pump. The cool-down rates and fluid stability of this configuration are evaluated. A prototypic test was performed to increase confidence in the design. That the helium panel cooldown rate agreed quite well with analytical prediction and was within acceptable limits. The design flow rate proved stable and two-phase pressure drop can be predicted quite accurately. Results confirm that a cooldown of the helium panel from 300 K to liquid helium temperature can be achieved in the few minutes available between plasma shots. Helium flow results indicate that, at the design flow rate of 5 g/s, flow will be stable for heat loads up to 54 W. The expected heat load on the helium panel during operation is about 10 W.<>
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