摘要
对聚变堆中心螺管(CS)线圈中,铠装电缆导体(CICC)中的SS316LN 不锈钢铠甲在运行状态下的断裂性能进行了测试分析。结果显示SS316LN 疲劳裂纹扩展性能较稳定,断裂韧性在经历冷变形与时效热处理后出现了大幅度衰减。此结果为未来核聚变堆超导线圈的设计与性能分析提供了数据参考。
Fracture properties of SS316LN tube of cable in conduit conductor (CICC) of fusion reactor central solenoid (CS) model coil is studied. The test results show that the SS316LN circle in square tube has low fatigue crack growth rate performance and the fracture toughness is decreased a lot after cold working and aging heat treatment. The results provide data reference for the design and performance analysis of superconducting coils in future nuclear fusion reactor.
作者
李向宾
金环
杨东昇
秦经刚
LI Xiang-bin;JIN Huan;YANG Dong-Sheng;QIN Jing-gang(China International Nuclear Fusion Energy Program Execution Center, Beijing 100038;Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031)
出处
《核聚变与等离子体物理》
CAS
CSCD
北大核心
2019年第2期165-168,共4页
Nuclear Fusion and Plasma Physics
