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Accurate decoupling current control of superconducting coils for nuclear fusion experiment system

机译:精确去耦电流控制核融合实验系统超导线圈

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The Large Helical Device (LHD) in the National Institute for Fusion Science (NIFS) is the largest helical type nuclear fusion experimental reactor using superconducting coils in the world. The system is composed of six superconducting coils with high mutual coupling and their power sources using thyristors from electrical circuit point of view. It shows non-linear characteristics due to eddy current through the structure around the coils, and accurate decoupling current control of the six coils is required. Two-degree-of-freedom H{sub}∞ controller has been designed and its performance has been tested at the simulator attached to the LHD system. Design of the controller and simulation results are presented.
机译:国家融合科学研究所(NIFS)中的大型螺旋设备(LHD)是世界上最大的螺旋型核融合实验反应器,在世界上使用超导线圈。该系统由六个超导线圈组成,具有高互联耦合及其电源,其使用来自电路的电路的晶闸管。它显示了由于涡流通过线圈周围的结构而导致的非线性特性,并且需要精确的六个线圈的去耦电流控制。已经设计了二维自由度H {Sub}控制器,并在连接到LHD系统的模拟器上测试了其性能。提出了控制器的设计和仿真结果。

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