Premium
First plasma experiment on spherical tokamak device UTST
Author(s) -
Imazawa Ryota,
Nakagawa Makoto,
Kamio Shuji,
Hihara Ryuma,
Yamada Takuma,
Inomoto Michiaki,
Takase Yuichi,
Ono Yasushi
Publication year - 2012
Publication title -
electrical engineering in japan
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.136
H-Index - 28
eISSN - 1520-6416
pISSN - 0424-7760
DOI - 10.1002/eej.21216
Subject(s) - plasma , tokamak , spherical tokamak , physics , atomic physics , beta (programming language) , merge (version control) , magnetic field , dense plasma focus , kinetic energy , nuclear engineering , nuclear physics , engineering , classical mechanics , computer science , quantum mechanics , information retrieval , programming language
The UTST (University of Tokyo Spherical Tokamak) device was constructed for the purpose of exploring the formation of ultrahigh‐beta ST (spherical tokamak) plasma using the double null plasma merging method. When two plasmas merge together to form a single plasma, magnetic field lines reconnect, and magnetic field energy is converted to plasma kinetic energy, increasing the plasma beta. Merging start‐up has been demonstrated in the TS‐3/4, START, and MAST devices using coils inside the vacuum vessel, and the TS‐3 plasma obtained a 50% beta. In order to demonstrate start‐up in a more reactor‐relevant situation, UTST has all poloidal field (PF) coils outside the vacuum vessel. The first plasma experiment on the UTST was begun in December 2007. In the results, the plasma obtained 10 kA by using only the outer PF coils and a single ST was generated in the lower area ( z = –0.3 to –1.0 m) close to a washer gun. This result suggests that another washer gun on the top of the UTST can allow the generation of ST in the upper area and merging start‐up by using outer PF coils. © 2012 Wiley Periodicals, Inc. Electr Eng Jpn, 179(2): 20–26, 2012; Published online in Wiley Online Library ( wileyonlinelibrary.com ). DOI 10.1002/eej.21216