First test results for the ITER central solenoid model coil

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Abstract

The largest pulsed superconducting coils ever built, the Central Solenoid (CS) Model Coil and Central Solenoid Insert Coil were successfully developed and tested by international collaboration under the R&D activity of the International Thermonuclear Experimental Reactor (ITER), demonstrating and validating the engineering design criteria of the ITER Central Solenoid coil. The typical achievement is to charge the coil up to the operation current of 46 kA, and the maximum magnetic field to 13 T with a swift rump rate of 0.6 T/s without quench. The typical stored energy of the coil reached during the tests was 640 MJ that is 21 times larger than any other superconducting pulsed coils ever built. The test have shown that the high current cable in conduit conductor technology is indeed applicable to the ITER coils and could accomplish all the requirements of current sharing temperature, AC losses, ramp rate limitation, quench behavior and 10 000-cycle operation.

Introduction

The ITER Central Solenoid (CS) Model Coil Program [1] has been carried out since 1992 as one of the largest R&D programs in the ITER Engineering Design Activity in an international collaboration among the ITER Joint Central Team (JCT), EU, Japan, Russia and US. In the program, the CS Model Coil (CSMC) and the CS Insert have been developed and tested in order to verify the magnet technology that will allow the ITER magnets to be built with confidence. It is expected to provide the validation of design and analysis tools, the demonstration of industrial manufacturing methods, the performance of each component integrated in the magnet and the demonstration of reliable operation.

Fabrication of the CSMC and CS Insert adopted a commingle-fabrication task sharing; all participants shared the fabrication of the Nb3Sn cable-in-conduit superconducting cables (24.6 tons). The US provided Incoloy 908 [2] as a conductor jacket material. The EU assembled the cables and the jacket into the conductors. The US assembled the CSMC Inner Module (10 layers) [3], and Japan assembled the Outer Module (eight layers) [4] and the CS Insert (one layer) [5]. Their configuration and major parameters are shown in Fig. 1 and Table 1, respectively. The CSMC is the largest pulsed superconducting magnet ever built with a stored energy of 640 MJ, at the operational current of 46 kA. Japan assembled these coil components coaxially as the CSMC and CS Insert in around 5 months within a 6.5-m diameter and 9.5-m high vacuum tank, as shown in Fig. 2, at the CSMC Test Facility [6] located at the Japan Atomic Energy Research Institute, Naka.

The cooldown of the coil system (total cold mass of 180 tons) was initiated by the end of November 1999 but a cold leak was detected at a coil temperature of around 20 K after around 500 h. Then the cooldown was cancelled, followed by warming up the coil. After the leak was repaired, the cooldown was resumed on March 13, 2000. The electric performance test was started in April and was successfully completed on August 18, followed by the coil warm-up which was finished by the end of August. The test implemented a total of about 350 charging runs and around 400 sensors continuously monitored the coil performance by the computer data acquisition system, accumulating a huge amount of test data. The cryogenic system also provided a stable 4-K condition through the test campaign without any problems. This paper introduces the test program, typical achieved operation, and the results of preliminary analysis.

Section snippets

Test program

The test program, the first mission of the CSMC and CS Insert electrical experiment, consists of the following three categories: DC test operation, AC test operation, and cyclic test for the CS Insert up to 10 000 cycles. The major test items in each category are listed in Table 2.

The coil operating current pattern depends on the power supply capacity. A DC power supply system consisting of one 50 kA/15 V and two 30 kA/12 V power supplies was used for the DC test operation and the cyclic test.

Typical demonstrated operations

Typical demonstrated operations are listed in Table 3. Three of the most typical operations are as follows: (1) Operating scenario of the ITER CS coil requests the maximum field change of −1.2 T/s from 13 T, simulating the plasma breakdown phase. To prove such operating scenario, the CSMC was fast discharged from 13 T with a time constant of 8.5 s, corresponding to a field change of −1.5 T/s (DC-3 in Table 3). Measured coil current, temperature and pressure in this condition are shown in Fig. 3

Current sharing temperature (Tcs) measurement

Current sharing temperature (Tcs) is one of the important test objectives to determine superconducting properties of the conductor used in both the CSMC and CS Insert, which will provide and determine a degradation of the superconducting properties and a required Ic margin through the coil fabrication. The Tcs measurements were carried out for the specific layer conductors, namely, the 1st layer and the 11th layer of the CSMC, and the CS Insert (one layer coil). The 1st layer is the innermost

Measurement of AC losses

This was the first measurement of AC losses for such a large CIC conductor as used in the CSMC and CS Insert that operate at high field and current up to 13 T, 46 kA with long conductor length from 90 to 150 m. Coupling losses for a long and large CIC conductor is of great interest. We therefore try to provide a few of the preliminary results of the measured AC losses for both the CSMC and CS Insert.

First, AC losses for the CSMC were measured by quickly discharging the coil from the specified

Ramp rate limitation

The instability induced by fast ramp-up has been reported as one of the unique instabilities for the superconducting pulsed magnet with the CIC conductor [12], [13]. Therefore, the existence of a ramp rate dependency of quench or ultimate operation current (ultimate operation magnetic field) was checked as one factor of the pulsed coil stability performance. It was measured on the CS Insert, varying its ramp rate up to 2.0 T/s with trapezoid current operation. Measured data, namely, the

Quench characteristics

To investigate the propagation of the normal zone, and the temperature and pressure rise during quench in the CIC conductor, quench test was performed using the CS Insert. An inductive heater, installed at the highest field region (the center of the conductor) was used to induce the quench. Thermometers and a pressure tap are also mounted at the central region to measure the maximum temperature and pressure rise in the quench. The test was carried out at a field of 13 T, keeping the initial

Tcs of the CS insert and cyclic test

Tcs of the CS Insert was investigated in detail since thermometers were mounted at the peak field position, allowed to measure the Tcs temperature directly. Tcs was measured at the specified current of 40, 30, 20, 10 and 1 kA, respectively. Critical current (Ic) measurement was simultaneously done at both 20 and 10 kA to check that the measured Tcs were the same as the Ic measurement. Then the CS Insert has the voltage tap pair located at the center turn with the length of 1.1 m. The Tcs and Ic

Conclusion

The CS Model Coil project, continuing over 8 years of international collaboration, has attained a significant milestone here through the first coil test. The CSMC and the CS Insert are obviously proved to satisfy and exceed almost all the ITER CS coil design criteria as shown in Table 4. Finally, we can say that the superconducting magnet technology has now developed to a level that will allow the ITER magnet to be built with confidence.

Acknowledgements

Well over 100 people from many countries and organizations participated in this large and very successful project. The authors are grateful to all who contributed to the project.

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