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我们使用分析程序SAITOKSCPF研究了KSTAR PF 超导线圈的运行特性.为了控制KSTAR超导托卡马克的运行等离子的外形以便实现受控热核聚变反应,在超导PF线圈内通过高变化率的运行电流.由于电磁感应,在超导线圈、支持结构和低温容器内产生感应电流和损耗.超临界氦流过CICC导体内部保持超导体运行在4.2K的温度.分析表明最大的温度在PF1线圈内部.在这篇论文中,我们对于单一和连续条件下等离子体放电对超导体运行的影响进行了研究.

The operating characteristics in the poloidal field (PF) coils system of KSTAR ( Korean Superconducting Tokamak Advanced Research ) for given operating scenarios are analyzed by SAITOKPF. In order to control the plasma shape in KSTAR to realize the thermal nuclear fusion reaction, the operating currents in PF coils are controlled with high various rate with respect to time. The induced current in the support structure and cryostat generates high eddy losses. It also produces the large hysteresis, eddy and coupling losses in superconducting coils. The supercritical helium with high velocity through the cable-in-conduit-conductor (CICC) removes the heat load to keep the temperature of superconducting cable lower than its current sharing temperature. The maximum temperature rise in PF1 is studied under the various inlet pressures for helium (He) while the output pressure of He is kept constant of 3Mpa. The single and continuous operating scenario for KSTAR are studied to decide the maximum temperature rise and total AC losses.

参考文献

[1] Qiu-liang Wang;Cheon Seong Yoon;Jin-liang He;Keeman Kim,Wohoo Chung.Operating Temperature Margin and Heat Load in PF Superconducting Coils of KSTAR[C].MT-17Geneva Switzerland,2001
[2] Qiuliang Wang;Cheon Seong Yoon;Sungkeun Baang .AC losses and heat removal in three-dimensional winding pack of Samsung superconducting test facility under pulsed magnetic field operation[J].Cryogenics,2001(4):253-265.
[3] L Bottura .A numerical model for the simulation of quench in the ITER magnets[J].Journal of Computational Physics,1996,125:26-41.
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