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首页> 外文期刊>IEEE Transactions on Applied Superconductivity >Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system
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Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system

机译:用于ITER磁体系统的70 kA高温超导体电流引线演示器的实验结果

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摘要

In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperature profile, the contact resistances, the heat load at 4.5 K, the required 50 K He mass flow rate, and the temperature margin were evaluated. The safety margin in case of a loss of He mass flow was studied, too. The paper describes the experimental results as well as the thermal and electrical models developed.
机译:在欧洲聚变技术计划的框架内,Forschungszentrum Karlsruhe和CRPP Villigen为使用高温超导体(HTS)的ITER TF线圈设计并制造了70 kA电流引线。 2004年初,HTS的电流导线在Forschungszentrum Karlsruhe的TOSKA设施中进行安装和测试。实验的范围是表征稳态条件下的电流引线,并探讨操作极限。为此,评估了温度曲线,接触电阻,4.5 K时的热负荷,所需的50 K He质量流量和温度裕度。还研究了氦质量流量损失情况下的安全裕度。本文介绍了实验结果以及开发的热和电模型。

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