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ITER TF导体压降流阻测试试验与分析 被引量:1

The pressure drop test and analysis of ITER TF conductor
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摘要 由于国际热核聚变实验堆(International Thermonuclear Experimental Reactor,简称ITER)的磁体系统运行时利用迫流氦进行冷却,迫流氦在线圈内部流动,产生一定阻力,会影响磁体线圈的正常工作,需要对磁体线圈进行压降测试。着重介绍线圈导体的流体测试试验,根据ITER纵向场(Toroidal Field,简称TF)的导体PA技术要求,搭建测试平台并在室温下进行氮气压降-流量测试实验。使用经验公式进行理论压降计算,计算结果与测量值进行对比,较为接近。同时,也利用该根导体参数进行低温下压降计算,计算结果和国外相关数据,相似。 The ITER (International Thermonuclear Experimental reactor) magnet system takes the supercritical helium as a medium for cooling, and then there would be some power loss to take an impact on the normal operation of the magnet due to the supercritical helium passing through the coil. So it is necessary to carry out the pressure drop test of the magnet coil. The paper focused on the pressure drop test for the coil conductor. According to ITER TF PA conductor technology requirements, a pressure drop test facility was set up in ASIPP and the test was performed with nitrogen gas at room temperature. The test results were well fit the values calculated by the experimental formula in different pressure drop. Meanwhile, the conductor parameters were calcu- lated in low temperature and the result was similar with data published in public journal.
出处 《低温与超导》 北大核心 2017年第7期19-23,78,共6页 Cryogenics and Superconductivity
基金 国际热核聚变实验堆(ITER)计划专项基金(2014GB105004)资助
关键词 国际热核聚变实验堆 纵向场导体 铠装电缆导体 压降 ITER, TF conductor, CICC, Pressure drop
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