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Featured researches published by T. Isono.


IEEE Transactions on Magnetics | 1996

Construction of ITER common test facility for CS model coil

S. Shimamoto; K. Hamada; Takashi Kato; H. Nakajima; T. Isono; T. Hiyama; M. Oshikiri; K. Kawano; M. Sugimoto; N. Koizumi; K. Nunoya; S. Seki; H. Hanawa; H. Wakabayashi; K. Nishida; T. Honda; H. Matsui; Y. Uno; K. Takano; T. Ando; M. Nishi; Yoshikazu Takahashi; S. Sekiguchi; T. Ohuchi; F. Tajiri; J. Okayama; Y. Takaya; T. Kawasaki; K. Imahashi; K. Ohtsu

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.


IEEE Transactions on Magnetics | 1996

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

K. Matsui; Yoshikazu Takahashi; M. Nishi; K. Nunoya; Takashi Kato; H. Nakajima; T. Hiyama; M. Sugimoto; T. Isono; K. Kawano; N. Koizumi; K. Hamada; T. Ando; H. Tsuji; S. Shimamoto; N. Shiga; N. Aoki; M. Ichihara

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.


IEEE Transactions on Magnetics | 1996

Design of the ITER central solenoid (CS) model coil

H. Ogata; T. Ando; T. Ito; K. Matsui; M. Sugimoto; Takashi Kato; H. Nakajima; M. Nishi; T. Isono; Yoshikazu Takahashi; H. Tsuji; S. Shimamoto; Y. Sumiyoshi; O. Osaki; T. Fujioka; K. Okuno

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.


IEEE Transactions on Magnetics | 1989

Recent progress in the demo poloidal coil program

H. Tsuji; K. Okuno; H. Nakajima; T. Ando; Yoshikazu Takahashi; M. Nishi; K. Yoshida; E. Tada; K. Koizumi; Takashi Kato; T. Isono; M. Oshikiri; T. Hiyama; K. Kawano; H. Yamamura; M. Sato; J. Yoshida; N. Itoh; S. Shimamoto; T. Satou; T. Ichihara

The fabrication of two 30-kA NbTi pulsed coils and one 10-kA Nb/sub 3/Sn coil with a total stored energy of 40 MJ is in progress as a part of the DPC (Demonstration Poloidal Coil) Program. All the Nb-Ti superconducting strands have been fabricated, and their loss time-constant has been measured at 0.32 ms at 7 T, which is well below the initial target of less than 1 ms. A novel winding technique is described for the large current conductor which provides good mechanical contact. >


IEEE Transactions on Magnetics | 1991

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

T. Ando; K. Okuno; H. Nakajima; K. Yoshida; T. Hiyama; H. Tsuji; Yoshikazu Takahashi; M. Nishi; E. Tada; K. Koizumi; Takashi Kato; M. Sugimoto; T. Isono; K. Kawano; M. Konno; J. Yoshida; H. Ishida; E. Kawagoe; Y. Kamiyauchi; Y. Matsuzaki; H. Shirakata; S. Shimamoto

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.


IEEE Transactions on Magnetics | 1996

Design of the CS insert coil [ITER superconducting coils]

M. Sugimoto; A. Terasawa; T. Isono; N. Koizumi; H. Nakajima; Takashi Kato; M. Nishi; Yoshikazu Takahashi; T. Ando; H. Tsuji; S. Shimamoto; K. Okuno; T. Ichihara; T. Sasaki; M. Hasegawa; T. Minato

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).


IEEE Transactions on Magnetics | 1992

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

M. Nishi; T. Ando; T. Isono; M. Sugimoto; N. Koizumi; K. Yoshida; K. Kawano; Yoshikazu Takahashi; Michitaka Ono; H. Tsuji; M. Ban; K. Oishi; Masaru Ikeda

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. >


IEEE Transactions on Magnetics | 1992

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

T. Ando; Yoshikazu Takahashi; K. Okuno; H. Tsuji; T. Hiyama; M. Nishi; E. Tada; K. Yoshida; K. Koizumi; H. Nakajima; Takashi Kato; M. Sugimoto; T. Isono; K. Kawano; M. Konno; J. Yoshida; H. Ishida; E. Kawagoe; Y. Kamiyauchi; S. Shimamoto

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. >


IEEE Transactions on Magnetics | 1994

Development of full-scale conductors for the ITER Central Solenoid Scalable Model Coils

T. Isono; K. Yoshida; Yoshikazu Takahashi; M. Nishi; M. Sugimoto; N. Koizumi; H. Nakajima; K. Hamada; K. Kawano; Takashi Kato; T. Hiyama; M. Oshikiri; H. Hanawa; S. Seki; H. Wakabayashi; H. Tsukamoto; U. Wadayama; H. Hosono; T. Sasaki; A. Miyake; H. Ebisu; S. Iwamoto; K. Okuno; T. Ando; H. Tsuji; R.J. Nelson

Japan Atomic Energy Research Institute (JAERI) has been developing 13-T, 40-kA conductors for the ITER Central Solenoid Scalable Model Coil. The conductors are composed of high performance (NbTi)/sub 3/Sn strands and titanium conduit. In this development work, 15-km length strand fabrication from a 100-kg billet, chrome plating, cabling of 675 or 768 strands, jacketing of titanium conduit, and so an were conducted by two mass production lines. In this paper, several test results are reported such as critical current measurements of full-scale conductors and AC loss measurements of sub-scale conductors. >


IEEE Transactions on Magnetics | 1992

Development of hollow cooling monolithic conductor for ITER TF coil

M. Sugimoto; T. Isono; N. Koizumi; K. Yoshida; Yoshikazu Takahashi; M. Nishi; T. Ando; H. Tsuji; T. Sekiguchi; S. Shimamoto; H. Tsukamoto; Y. Kurumizawa

Results of verification tests for the TMC (Test Module Coil)-FF hollow cooling monolithic conductor are presented. With various strands to test the optimal bronze ratio, the critical current of full-scale samples was measured at 13 T and 4.2 K. The maximum critical current density is 404 A/mm/sup 2/, which is smaller than the requirement of over 500 A/mm/sup 2/ at 12 T. There is no degradation of the critical current of a full size conductor compared with the same sample before cabling. AC losses of the conductor were measured in parallel and perpendicular fields. The results of the time constant measurements are larger than the calculated values in each direction. The stability margin of the full size conductor is 40 mJ/cc-metal at the nominal point, assuming long length disturbance. This result is estimated from experimental results for a reduced size conductor and from thermal analysis. The heat generation of the joint between Nb/sub 3/Sn and Nb-Ti is much smaller than that of nuclear heating. >

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M. Nishi

Japan Atomic Energy Research Institute

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Yoshikazu Takahashi

Japan Atomic Energy Research Institute

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H. Tsuji

Japan Atomic Energy Agency

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H. Nakajima

Japan Atomic Energy Research Institute

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K. Kawano

Japan Atomic Energy Agency

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K. Okuno

Japan Atomic Energy Agency

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K. Yoshida

Japan Atomic Energy Research Institute

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S. Shimamoto

Japan Atomic Energy Research Institute

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T. Hiyama

Japan Atomic Energy Agency

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