Superconducting magnet system in a fusion reactor
Superconducting magnet system in a fusion reactor
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DOI：
10.1016/j.jnucmat.2004.04.151
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发表时间：
2004-08
影响因子：
3.1
通讯作者：
K. Okuno;A. Shikov;N. Koizumi
中科院分区：
文献类型：
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作者：
K. Okuno;A. Shikov;N. Koizumi
托卡马克聚变反应堆中的环向场（TF）线圈具有较高的磁场强度，可以提供更好的反应堆性能。因此，聚变磁体的发展总是推动新的超导体在工业基础上用于大型磁体。用于国际热核聚变实验反应堆（ITER）的磁体使用Nb3Sn以产生13 T的峰值磁场。经过ITER的广泛发展，包括模型线圈的研制，Nb_3Sn超导体技术取得了重大进展。下一代超导体Nb3Al具有在较高场下的大临界电流密度和与Nb3Sn相比由于应变引起的较小的临界电流退化的突出特征。高温超导体（HTS）是另一个候选者，如果它变得可用，可以在大型磁体中实现20 T以上的磁场。这些材料有可能用于高性能聚变堆。
Higher magnetic field of a Toroidal field (TF) coil in a tokamak fusion reactor can offer better performance of the reactor. Therefore, fusion magnet development always drives a new superconductor to be used in a large magnet on an industrial basis. Magnets for the International Thermonuclear Experimental Reactor (ITER) use Nb3Sn in order to generate a peak magnetic field of 13 T. Technologies for Nb3Sn superconductor has made a significant progress through the extensive development in ITER including the manufacture of model coils. A next generation superconductor, Nb3Al, has outstanding features of large critical current density at higher field and smaller degradation of the critical current due to a strain compared to Nb3Sn. High temperature superconductor (HTS) is another candidate, and if it becomes available, a magnetic filed above 20 T can be realized in a large magnet. These materials have the possibility of being used for high performance fusion reactors.