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Current Sharing Temperature Test and Simulation with GANDALF Code for ITER PF2 conductor Sample

Plasma Science and Technology 2011年第5期13卷 627-630页

作者：李少磊武玉刘勃翁佩德 Institute of Plasma Physics Chinese Academy of Sciences

cable-in-conduit conductor （CICC） conductor sample of the PF2 coil for ITER was tested in the SULTAN facility. According to the test results, the CICC conductor sample exhibited a stable performance regarding the current sharing temperature. Under the typical operational conditions of a current of 45 kA, a magnetic field of 4 T and a temperature of 5 K for PF2, the test result for the conductor current sharing temperature is 6.71 K, with a temperature margin of 1.71 K. For a comparison thermal-hydraulic analysis of the PF2 conductor was carried out using GANDALF code in a 1-D model, and the result is consistent with the test one.

关键词： current sharing temperature poloidal field cable-in-conduit conductor NbTistrand GANDALF

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CICC Joint Development and Test for the Test Facility

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Plasma Science and Technology 2005年第1期7卷 2629-2631页

作者：武玉翁佩德 Institute of Plasma Physics Chinese Academy of Sciences Hefei 230031 China

The superconducting joint of the NbTi cable-in -conduit conductor (CICC) has been developed and tested on the magnet test facility at Institute of Plasma Physics, Chinese Academy of Sciences. The CICC is composed of (2NbTi+lCu)x3x3x(6+ltube) strands each with 0.85 mm in diameter, which has been developed for a central solenoid model coil. The effective length of the joint is about 500 mm. There have been two common fabrication modes, one of them is to integrate the 2 CICC terminals with the copper substrate via lead-soldering, and the other is to mechanically compress the above two parts into an integrated unit. In the current range from 2 kA to 10 kA the joint resistance changes slightly. Up to now, 11 TF magnets, a central solenoid model coil, a central solenoid prototype coil, and a large PF model coil of PF large coil have been completed via the latter joint in the test facility.

关键词： cable-in-conduit conductor superconducting joint joint resistance

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The Investigation on Welding Processes for SUS316LN Tubes Used in Superconducting Magnetic System of EAST

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Plasma Science and Technology 2005年第4期7卷 2932-2935页

作者：吴杰峰陈思跃翁佩德高大明 Institute of Plasma Physics Chinese Academy of Sciences Hefei 230031China

The force flow cooled superconducting cable-in-conduit conductor （CICC） is used in both of EAST toroidal field （TF） and poloidal field （PF） coils. The conductor consists of multi-stage NbTi superconducting cable and 1.5 mm thick square jacket. The cable is pulled through in a thin wall circular jacket and then compacted to square cross-section conductor. The jacket material is SUS316LN austenitic stainless steel seamless tubes （about 10 m each）, which is assembled by butt-welding up to 600 m. The results of the welding procedure investigation and quality assurance procedures carrying out are described in this paper.

关键词： cable-in-conduit conductor SUS316LN austenitic stainless steel automatic welding and quality assurance

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