著者

本島 修

出版者

CRYOGENICS AND SUPERCONDUCTIVITY SOCIETY OF JAPAN

雑誌

低温工学 (ISSN:03892441)

巻号頁・発行日

vol.32, no.11, pp.540-547, 1997-11-25 (Released:2010-02-26)

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The Large Helical Device (LHD) is a heliotron-type toroidal fusion experimental device which will provide useful and reliable datasets for high-temperature helical plasmas with an equivalent Q value of 0.1 to 0.35. One of the crucial tasks of LHD is to demonstrate steady-state operations by taking the advantage of its magnetic configuration with currentless plasmas as well as built-in divertors. In this respect, the coil systems are fully superconducting (SC); consisting of a pair of helical coils, three pairs of poloidal coils and nine bus lines. All the SC coils have been successfully fabricated with high accuracy and they are presently in the final stage of assembly in a cryostat vessel along with outside preparations of plasma heating devices, diagnostic equipment and control systems. The first plasma operation is scheduled for the end of March 1998. The technological development of SC magnets through this project played a key role in LHD, and will also be useful for constructing future fusion reactors.

著者

本島 修 大西 正視 飯吉 厚夫

出版者

社団法人 プラズマ・核融合学会

雑誌

核融合研究 (ISSN:04512375)

巻号頁・発行日

vol.38, no.2, pp.205-223, 1977 (Released:2011-03-04)

参考文献数

14

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We propose the possibility to ignite the D-D reactor from the D-T reactor by increasing the deuterium density and reducing the tritium density. Supposing that the D-T reactor has been already realized and the plasma parameters are in the Trapped Ion Regime, the D-D reactor is possibly ignited by continuously developing the plasma parameters from the D-T reactor. The dynamics of the transition is calculated, and it becomes clear that the additional heating in the initial state is very effective. The characteristics of the D-D reactor are also shown. The loss rate of tritium from the core plasma is one order less than that of the conventional D-T reactor. At last the modified D-T reactor which is aimed to improve the tritium breeding ratio in the Li blanket is introduced.

著者

本島 修

出版者

社団法人プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.73, no.3, pp.353-354, 1997-03-25