Hansheng Feng

Test of a 10 kA HTS Current Lead for ITER

The ITER Organization (IO) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly developing the design of the 10 kA Current Leads (CL) using High Temperature Superconductors (HTS) for the Correction Coil (CC) Magnet System of the International Thermonuclear Experimental Reactor, ITER. The proposed design combines a conventional helium cooled heat exchanger operating between 65 K and 300 K with a HTS module covering the low temperature end using Bi-2223 tapes. The details of the design and test results obtained on a first prototype lead will be discussed in this paper.

Development of 12 kA HTS Current Lead for Accelerator Magnet Test Application

A pair of 12 kA HTS current leads has been developed with a nitrogen vapor cooled resistive section and a stainless steel shunted HTS section using Bi2223/AgAu matrix tapes at the Institute of Plasma Physics, Chinese Academy of Science. These two leads, which need to transfer 21 kA in a short time, are intended as replacement leads for the accelerator magnet test program at the Joint Institute of Nuclear Research in Dubna. The structure design of the current leads is described. The test results are reported and discussed in this paper.

Results of the Testing of ITER CC HTS Current Lead Prototypes

According to the procurement agreement with the International Thermonuclear Experimental Reactor project, the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) in China is responsible for the construction and performance testing of 31 sets of feeder systems, which contain also 60 high-temperature superconducting (HTS) current leads. In 2014/2015, three pairs of prototype current leads of three different types are being built and tested. A first pair of correction coil (CC) type, 10-kA current lead prototypes was built and cold tested in ASIPP in early 2015. The test items cover the joint resistance, overheating time test, mass flow consumption in steady-state operation for various currents, and the pulsed current scenario test. This paper presents the test results for the prototype CC 10-kA HTS current leads.

New Facility for the Cryogenic Test of ITER Current Leads at ASIPP

Based on the procurement agreement signed by the ITER IO and the Chinese domestic agency, the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) will produce the 60 single high-temperature superconducting (HTS) current leads in-kind for ITER. All of the ITER HTS current leads will be cold tested before assembly in the coil feeder systems. Therefore, a dedicated test facility was built in 2011 and completed in 2014 to perform the factory acceptance test of the HTS current leads. This paper describes the design of the test facility and its key components, including the cryogenic system, the power supply system, and the data acquisition as well as quench detection system. As an example, some results of the ITER HTS current lead prototype test campaigns will be shown.

Progress of the ITER Feeder in China

The Procurement of Feeder system in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) for The International Thermonuclear Experimental Reactor (ITER) Tokamak device has been carrying out after the signature of Procurement Arrangement in October 2011. The relevant main tasks in 2012 and 2013 are the qualification of some key subcomponents, including high temperature superconducting current leads (HTS-CL), superconducting joints, 80-K thermal shield (TS), vacuum barrier, in-cryostat feeder, cold mass support, etc. The production of manufacturing drawings, preparation of manufacturing plan, manufacture and qualification of tooling, and qualification of subcomponents are all involved in this phase. This paper describes the progress made by ASIPP and some sub-contractors for the feeders qualification work.

Investigating the 10 kA HTS Module of the ITER Current Leads

The International Thermonuclear Experimental Reactor (ITER) has 60 high-temperature superconducting (HTS) current leads (CL) which have a nominal current of 68, 55 and 10 kA (depending on the type of magnet they have to supply) and provide a total current of 2.7 MA to the magnet system. The HTS module is a key part of CLs. This paper describes the simulation of the critical current in a multi-layer tape model as well as the special soldering technique developed for the HTS stack. In order to validate this technique, a 10 kA pre-prototype HTS module was made and tested in a setup that reproduces ITER conditions at ASIPP. The paper also briefly describes the overheating time test setup and the results.

Design and Technology Preparation for the ITER HTSCL

ASIPP will supply for ITER all the current leads. There are three types of high temperature superconducting (HTS) current leads designed to carry 68 kA, 55 kA, or 10 kA to the ITER magnets. Different from the trial leads manufactured and tested in Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), some critical technologies were qualified before the manufacturing of the ITER leads could commence, including: 1) welding, brazing, and soldering qualification; 2) fin type heat exchanger (HEX) with tight assembly tolerance; 3) low temperature superconducting (LTS) linker with cables soldered to the 5 K copper terminal; 4) instrumentation mock-up for the temperature and voltage test. In this paper, the outcome of these qualification activities will be reported together with the plans for the series production planning and development.