New design of cable-in-conduit conductor for application in future fusion reactors
New design of cable-in-conduit conductor for application in future fusion reactors
复制标题
适用于未来聚变反应堆的电缆套管导体的新设计
DOI：
10.1088/1361-6668/aa8900
复制
发表时间：
2017-11-01
影响因子：
3.6
通讯作者：
Devred, Arnaud
中科院分区：
文献类型：
--
作者：
Qin, Jinggang;Wu, Yu;Devred, Arnaud
中国聚变工程试验堆（CFETR）是一种新型托卡马克装置，其磁体系统包括环向场、中心螺线管（CS）和极向场线圈。主要目标是建造一个聚变功率约为1吉瓦、由包层自给自足的聚变工程托卡马克反应堆。为了达到这一高性能，磁场目标为15 T。然而，高场和高电流所产生的巨大电磁负载是循环下导体退化的威胁。具有短捻距（STP）设计的导体具有大的刚度，这使得能够在负载和热循环方面显著提高性能。但STP设计的导线有一个显着的缺点：在布线过程中容易造成严重的股线压痕。压痕会降低股线性能，特别是在高载荷循环下。为了克服这一缺点，提出了一种新的设计。这种新设计的主要特点是在三重更新布局。三合线由两条Nb3Sn绞线和一条软铜绞线组成。两个Nb3Sn股线的捻距大并且首先成缆。然后将铜股线以较短的捻距缠绕在两个超导股线（CWS）周围。以下电缆级的布局和绞距类似于具有STP设计的ITER CS导体。制造了一个与ITER CS尺寸相似的短导体样品，并使用Twente Cable Press进行了测试，以研究其机械性能、交流损耗和破坏性检查的内部检查。将结果与STP导体（ITER CS和CFETR CSMC）测试进行比较。结果表明，新的导体设计具有相似的刚度，但比STP设计低得多的股线压痕。新的设计显示了在未来聚变反应堆中的应用潜力。
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device whose magnet system includes toroidal field, central solenoid (CS) and poloidal field coils. The main goal is to build a fusion engineering tokamak reactor with about 1 GW fusion power and self-sufficiency by blanket. In order to reach this high performance, the magnet field target is 15 T. However, the huge electromagnetic load caused by high field and current is a threat for conductor degradation under cycling. The conductor with a short-twist-pitch (STP) design has large stiffness, which enables a significant performance improvement in view of load and thermal cycling. But the conductor with STP design has a remarkable disadvantage: it can easily cause severe strand indentation during cabling. The indentation can reduce the strand performance, especially under high load cycling. In order to overcome this disadvantage, a new design is proposed. The main characteristic of this new design is an updated layout in the triplet. The triplet is made of two Nb3Sn strands and one soft copper strand. The twist pitch of the two Nb3Sn strands is large and cabled first. The copper strand is then wound around the two superconducting strands (CWS) with a shorter twist pitch. The following cable stages layout and twist pitches are similar to the ITER CS conductor with STP design. One short conductor sample with a similar scale to the ITER CS was manufactured and tested with the Twente Cable Press to investigate the mechanical properties, AC loss and internal inspection by destructive examination. The results are compared to the STP conductor (ITER CS and CFETR CSMC) tests. The results show that the new conductor design has similar stiffness, but much lower strand indentation than the STP design. The new design shows potential for application in future fusion reactors.