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Performance evaluation of the ITER Toroidal Field Model Coil Phase I

机译:ITER环形场模型线圈I期的性能评估

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摘要

The International Thermonuclear Experimental Reactor Toroidal Field Model Coil, a large (2.7 m X 3.8 m X 0.8 m) superconducting (Nb_3Sn) DC coil designed and constructed in collaboration between EU industries and laboratories coordinated by European Fusion Development Agreement, has been tested during 2001 in the TOSKA cryogenic facility at Forschungszentrum Karlsruhe, Germany, achieving the nominal 80 kA at 7.8 T peak field and 86 MJ stored energy as a standalone coil (Phase I). Possibly the highlight of the tests was the measurement of the current sharing temperature (T_(CS)) at different transport currents I in the self-field of the coil. The measurement method is discussed, based also on the two-year long predictive work, which preceded it. The results of the full set of T_(CS) measurements at I = 80, 69 and 57 kA are presented here, and evaluated in a companion paper (part 2).
机译:国际热核实验堆环形场模型线圈是一种大型(2.7 m X 3.8 m X 0.8 m)超导(Nb_3Sn)直流线圈,由欧盟工业和实验室根据欧洲聚变发展协议的协调设计和制造,已于2001年进行了测试在德国卡尔斯鲁厄Forschungszentrum的TOSKA低温工厂中,在7.8 T的峰值磁场下实现了标称80 kA的电流,并且作为独立线圈(第一阶段)存储了86 MJ的能量。可能的测试重点是在线圈的自磁场中在不同传输电流I下测量均流温度(T_(CS))。讨论了该测量方法,同时还基于之前的为期两年的长期预测工作。此处提供了I = 80、69和57 kA时的完整T_(CS)测量结果,并在随附的论文中进行了评估(第2部分)。

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