Design and related experiments of JT-60 divertor coils.
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概要
- 論文の詳細を見る
The JT-60 divertor coils produce a separatrix configuration in divertor operations of <BR>JT-60. A suitable separatrix configuration was obtained for a plasma current of 2.1 MA <BR>with coil ampere turns of ± 0.755 MAT. A high primary membrane stress of 52 MPa was permissible at the welded joints of the copper conductor made on the site. The mechanical strength of the joints welded in a factory was also improved by means of a press treatment. Electric insulation materials were selected considering a degradation of withstand voltage characteristics due to high cyclic mechanical strain. Vacuum-tight coil cases were composed of rigid rings and U-shaped bellows made of Inconel-625 <BR>alloy, and designed to withstand plasma disruption with a current decay time constant of 3 ms. The maximum temperature of the conductor in the periodic operation of divertor discharges was below 155°C which was the allowable temperature of the coil insulation. Molybdenum armor plates coated with titanium carbide and Inconel-625 <BR>bellows cover plates were attached against high heat flux from plasma. Thermal and mechanical load tests were carried out using component models to evaluate their performance in advance of the final fabrication of the actual coils. The satisfactory performance of the divertor coils were demonstrated in the pre-operational power test.
- 一般社団法人 日本原子力学会の論文
著者
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WATANABE Takashi
Hitachi Ltd.
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SHIMIZU Masatsugu
Japan Atomic Energy Research Institute
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TERUYAMA Kazuhiro
Hitachi Works, Hitachi Ltd.
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ANDO Toshiro
Japan Atomic Energy Research Institute
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OHKUBO Minoru
Japan Atomic Energy Research Institute
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NAKAMURA Yukiharu
Japan Atomic Energy Research Institute
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OHTA Mitsuru
Japan Atomic Energy Research Institute
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