Effect of coil configuration parameters on the mechanical behavior of the superconducting magnet system in the helical fusion reactor FFHR
Effect of coil configuration parameters on the mechanical behavior of the superconducting magnet system in the helical fusion reactor FFHR
复制标题
线圈配置参数对螺旋聚变反应堆FFHR中超导磁体系统力学行为的影响
DOI：
10.1016/j.fusengdes.2019.01.029
复制
发表时间：
2019
影响因子：
1.7
通讯作者：
H. Hashizume
中科院分区：
文献类型：
--
作者：
H. Tamura;T. Goto;N. Yanagi;J. Miyazawa;T. Tanaka;A. Sagara;S. Ito;H. Hashizume
FFHR-d1 A和c1是螺旋聚变反应堆的概念设计。超导线圈之间的位置关系，一对螺旋线圈与两套垂直场线圈，观察到在两种类型的FFHR相似。线圈配置的这种关系是基于在国家聚变科学研究所设计和建造的大型螺旋装置的线圈配置。对于实现优化的线圈配置以预期等离子体约束条件的改善的需求日益增加。在这项研究中，FFHR的线圈配置的基本参数集的基础上的结构设计，它满足结构的合理性。进一步研究了线圈结构参数对应力分布的影响。还讨论了曲率半径对螺旋线圈的缠绕方案的影响。
FFHR-d1A and c1 are the conceptual design of a helical fusion reactor. The positional relationship among superconducting coils, a pair of helical coils with two sets of vertical-field coils, are observed to be similar in both type of FFHR. Such a relation of coil configuration is based on the coil configuration of the Large Helical Device, which has been designed and constructed at the National Institute for Fusion Science. There is increasing demand to achieve an optimized coil configuration to anticipate improvements in plasma-confinement conditions. In this study, the structural design of FFHR based on the fundamental set of parameters of coil configuration is depicted, which satisfies the soundness of the structure. Further, the effects of the coil configuration parameters on the stress distributions are investigated. An effect of radius of curvature on a winding scheme of the helical coil is also discussed.