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ITER用极向场线圈导体短样分流温度测试

Current Sharing Temperature Test of Short Conductor Sample for ITER Poloidal Field Coils
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摘要 ITER用极向场(PF)线圈CICC导体短样是用西部超导材料科技有限公司提供的NbTi超导股线绕制完成,该股线在不同温度下的临界电流测试性能稳定,符合绕制导体的要求。对PF导体短样在SULTAN实验室进行了测试,经电磁循环通电前后,分流温度无较大改变,导体性能稳定。在考虑了导体自场作用的情况下,导体在5T、50kA运行环境下的分流温度为6.33K,满足ITER规定的要求。 The NbTi cable-in-conduit conductors for the ITER poloidal field (PF) coils were fabricated using the strands offered by Western Superconducting Technologies Co. , Ltd. The performance of strands is stable in critical current test at different tem- peratures. The short PF conductor sample was tested in SULTAN laboratory. Before and after electromagnetic cycle, the current sharing temperature is not obviously changed and the conductor performance is stable. Considering the self field of conduc- tor, the conductor's current sharing temperature is 6.33 K at 5 T and 50 kA, which satisfies the ITER requirements.
作者 刘勃 武玉
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2011年第12期1511-1515,共5页 Atomic Energy Science and Technology
基金 国家重点基础研究发展计划资助项目(0559730532)
关键词 分流温度 ITER NBTI 极向场导体 SULTAN 自场 current sharing temperature ITER NbTi poloidal field conductor SUL-TAN self field
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参考文献6

  • 1BRUZZONE P,WESCHE R,STEPANOV B.Qualification tests and facilities for the ITER su-perconductors[].Nuclear Fusion.2009
  • 2BRUZZONE P,BAGNASCO M,BESSETTED.Test results of the ITER PF insert conductorshort sample in SULTAN[].IEEE Trans ApplSupercond.2005
  • 3BESSETTE D.DC performance analysis of NbTiand Nb3Sn ITER relevant cable-in-conduit con-ductors[].IEEE Transactions on Applied Superconductivity.2005
  • 4Mitchell N,Bessette D,Gallix R.The ITER Magnet Sys-tem[].IEEE TransApplSuper.2008
  • 5Mitchell N,Bauer P,Bessette D,et al.Status of theITER magnets[].Fusion Engineering.2009
  • 6Weng P D,Bruzzone P,Chen Z M,et al.Test results and analyses of conductor short samples for HT-7U[].Cryogenics.2003

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