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1996•IEEE Transactions on MagneticsRequires access

Design of the ITER central solenoid (CS) model coil

Hisanao OGATA, Toshiki Ando, T. Ito, Katia Nicolau Matsui, Makoto Sugimoto, Takashi Kato, Hideo Nakajima, M. Nishi, T. Isono, Yoshikazu Takahashi, Hiroshi Tsuji, Susumu SHIMAMOTO, 幸博 住吉, O. Osaki, Toshiyuki Fujioka, Kazuki Okuno

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Abstract

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.

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What this paper is about

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.

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Available abstract

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.

Key concepts: Electromagnetic coil, Thermonuclear fusion, Solenoid, Nuclear engineering, Electrical conductor, Fusion power, Materials science, Toroidal field

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