管内电缆导体传输交流损耗的理论计算和实验

Theoretical and Experimental Study on Transport Current Loss for Cable-in-Conduit Conductors

交流损耗是大型超导核聚变实验装置如国际热核聚变实验堆和中国聚变工程实验堆稳定性的重要指标。然而应用于核聚变装置的管内电缆导体(CICC)在无外场下传输损耗数值计算很少。首先分析基于分布参数等效电路方法对CICC的N根股线的电流进行描述和分析;之后算出整个导体的电流分布,从而求出导体的传输电流损耗;同时,将数值计算结果与临界态模型结果作对比,以验证该计算模型的可行性;提出改进的CICC交流损耗测量方法,为国内下一步测试CICC及其线圈奠定了实验基础;最后,提出适用于单根圆股线的定标法则,为计算CICC的传输电流损耗奠定理论基础。

For practical applications of large superconducting nuclear fusion experimental devices,such as international thermonuclear experimental reactor and China fusion engineering test reactor,AC loss is the main criteria on the stability performance. Considering the numerical calculation on transport AC loss of Nb Ti/Nb3 Snbased strands and cable-in-conduit conductors( CICCs) for nuclear fusion magnets was rarely presented before,a distributed parameter equivalent circuit model of N-strands conductors for current analysis was investigated. Based on the current distribution of the whole cable,the transport current loss was calculated. Meanwhile,the results were compared to the critical state( CS) model to verify the feasibility of the proposed model. Finally, an improved experimental system was proposed,which gives a good reference for next step CICC cables and coils measurement. Further,a scaling law of single strand was obtained,which lays the foundation of transport current loss calculation for CICCs.