M. Sugimoto

Construction of ITER common test facility for CS model coil

Japan Atomic Energy Research Institute is constructing the International Thermonuclear Experimental Reactor common test facility for the Central Solenoid Model Coil which is around 180 tons, a forced-flow cooled magnet with the maximum pulsed operation of 2 T/s and generates the rated magnetic field of 13 T at 48 kA with stored energy of 668 MJ. The test facility consists of a coil vacuum chamber, a cryogenic system with the 5-kW refrigerator and 500-g/s cryogenic pump, two pairs of 50-kA current leads, two DC power supplies (50 kA and 60 kA) and two JT-60 pulsed power supplies (50 kA, /spl plusmn/4.5 kV and /spl plusmn/40 kA, /spl plusmn/1.5 kV). The facility will be demonstrating the refrigeration and operation of a fusion pulsed magnet and the design and construction will accumulate experience towards the construction of ITER.

Critical current measurements using 13-T split coils and 100-kA superconducting transformer (for FER)

A description is given of a large scale superconductor test facility composed of a 13-T magnetic field and a 100-kA sample current. A superconductor transformer with a 100-kA secondary conductor was fabricated as a current amplifier in order to supply the 100-kA sample current. Superconducting split coils with 100-mm clear bore diameter were fabricated, and a 13-T available field was generated by these coils. Both the 100-kA superconducting transformer and the 13-T superconducting split coils were installed in a 2-m-diameter FRP dewar for the purpose of testing large-scale superconductors. A description is given of the performance of the 100-kA superconducting transformer and the 13-T superconducting split coils as well as the results from critical current measurements of prototype conductors for toroidal coils.

Design and fabrication of superconducting cables for ITER central solenoid model coil

The Nb/sub 3/Sn cable is being fabricated for the central solenoid (CS) model coil under the ITER Engineering-Design Activity. The cable consists of about 1000 strands whose diameter is 0.81 mm. The design current is 48 kA at a magnetic field of 13 T. The 0.6-GJ CS model coil is operated in a pulse mode (0.5 T/s). The first trial fabrication of a 100-m dummy cable and a 20-m superconducting cable was completed successfully. The second trial fabrication of a 1000-m dummy cable was performed to establish the stable manufacturing procedure in January, 1995. The authors measured the AC losses of the full-sized conductor and could determine the cable coupling time constant. They analyzed the heat generation of the CS model coil and calculated the temperature rise of the cable for the model coil.

Design consideration of the ITER-TF coil with a react-and-wind technique using Nb/sub 3/Al conductor

The ITER-TF coil requires a generation of 12.5 T in a size of 12 m/spl times/18 m. For such a high field-large coil, the applicability of Nb/sub 3/Al conductors was considered with a react-and-wind technique which realizes high reliability and low cost for the coil fabrication. The maximum bending strain on the Nb/sub 3/Al conductor in use of this technique is 0.39%. I/sub c/ degradation due to the strain is expected to be below 5%. The limiting current is estimated as 65 kA for 60 kA operation current. AC loss in the TF coil with Nb/sub 3/Al conductor is almost the same as with Nb/sub 3/Sn conductor.

Design of the ITER central solenoid (CS) model coil

The Japan Atomic Energy Research Institute (JAERI) has been designing and developing the central solenoid (CS) model coil for International Thermonuclear Experimental Reactor (ITER). The CS model coil is composed of two modules and they will be manufactured by a United States Home Team and a Japanese Home Team. The coil winding method is two-conductors-in-hand and the coil, which has an inner diameter of 1.6 m and an outer diameter of 3.6 m, produces a maximum field of 13 T. The coil will be tested in the JAERI facility. This paper describes the coil design, manufacturing procedure, stress analysis on the winding pack and AC loss analysis.

Design of the Nb/sub 3/Al insert to be tested in ITER central solenoid model coil

Critical current of Nb/sub 3/Al is less sensitive to strain than Nb/sub 3/Sn. This characteristic makes a react-and-wind method applicable in a large dimension coil. By applying the react-and-rind method for toroidal field (TF) coil, technical difficulties in transfer of the conductor after reaction are eliminated and construction cost of magnet system can be reduced in comparison with a wind-react-insulate-transfer method. Therefore, the Nb/sub 3/Al conductor has large potential as candidate for the TF conductor. The experiment of a 60 kA-12.5 T Nb/sub 3/Al insert is projected to demonstrate applicability of the react-and-wind method with the Nb/sub 3/Al conductor. The react-and-wind method will be employed in the winding and 0.4% bending strain will be applied to the conductor. The major characteristics of the Nb/sub 3/Al insert are reported in this paper.

Experimental results of the Nb/sub 3/Sn demo poloidal coil (DPC-EX)

In order to demonstrate the applicability of a Nb/sub 3/Sn conductor to pulsed poloidal coils for Tokamak fusion machines, the Nb/sub 3/Sn Demo Poloidal Coil (DPC-EX) has been fabricated and tested. DPC-EX, whose inner diameter is 1 m, consists of two double pancakes made by a react-and-wind technique. The coil has a flat cable-in-conduit conductor cooled by forced-flow helium. DPC-EX has been set up in the Demo Poloidal Coil Test Facility (DPCF). In the operation of the coils in series, DPC-EX has been ramped up to 17 kA in 1 s. The magnetic field at this point was 6.7 T, and pulsed operation at 6.7 T/s was thus demonstrated. An average current density of 37.2 A/mm/sup 2/ in the winding was achieved in this operation, and the AC loss of the coil was confirmed to be quite small.

Design of the CS insert coil [ITER superconducting coils]

The Engineering Design Activity (EDA) of International Thermonuclear Experimental Reactor (ITER) has been carried out since 1992 among the four Parties which are European Union, Japan, Russian Federation, and United States. The design and the fabrication of the center solenoid (CS) model coil is underway in the ITER-EDA. The CS model coil consists of four parts, which are the outer module, the inner module, insert and the supporting structure. The design of the CS insert coil is reported and discussed. The inner diameter of the CS insert coil is 1.5 m. The conductor of the CS insert coil is the same as that of the ITER-CS coil. The CS insert coil will be installed inside the CS model coil. The conductor performance will be demonstrated on the maximum magnetic flux density of 13 T at the test facility of Japan Atomic Energy Research Institute (JAERI).

Development of 240 mm bore-13 T superconducting coil for large scale conductor testing

A 240-mm-bore high-field superconducting coil was designed, fabricated, and tested. This coil is planned as a test facility for the development of large-scale superconductors for fusion machines. Tests were performed in a 4.2 K bath, and the designed magnetic flux density of 13.0 T was obtained in the center of its bore. The maximum magnetic flux density on the coil was 13.9 T; the average current density was 101 A/mm/sup 2/; the stored energy was 4.8 MJ; and the charging time was 18.5 minutes. This coil has served as a reliable conductor test facility since the first achievement of 13.0 T. >

AC loss results of the Nb/sub 3/Sn Demo Poloidal Coil (DPC-EX)

AC losses in the DPC-EX, whose purpose is to demonstrate the applicability of Nb/sub 3/Sn conductor to poloidal coils for Tokamak fusion machines, were measured, and the results were analyzed. The coil was fabricated with a Nb/sub 3/Sn cable-in-conduit conductor and has a 1 m inner diameter. The AC loss was 9.4 kW for the pulse operation of a 0-17 kA-0 cycle with a ramp time of 1 s, corresponding to a 6.7-T maximum field and a 6.7-T/s pulse rate. It was 0.14% of the magnetic stored energy. The effective Nb/sub 3/Sn filament diameter was estimated as 32 mu m and the effective time constant of the coupling current within the strand was calculated as 2 ms on the assumption that coupling current between strands is negligible. The limitation of coil current due to AC losses is discussed. >