TY - JOUR
T1 - Steady-state operation scenario and the first experimental result on QUEST
AU - Hanada, Kazuaki
AU - Sato, Kohnosuke
AU - Zushi, Hideki
AU - Nakamura, Kazuo
AU - Sakamoto, Mizuki
AU - Idei, Hiroshi
AU - Hasegawa, Makoto
AU - Takase, Yuichi
AU - Mitarai, Osamu
AU - Maekawa, Takashi
AU - Kishimoto, Yasuaki
AU - Ishiguro, Masaki
AU - Yoshinaga, Tomokazu
AU - Igami, Hiroe
AU - Nishino, Nobuhiro
AU - Honma, Hiroshi
AU - Kawasaki, Shoji
AU - Nakashima, Hisatoshi
AU - Higashijima, Aki
AU - Higashizono, Yuta
AU - Ando, Akira
AU - Asakura, Nobuyuki
AU - Ejiri, Akira
AU - Hirooka, Yoshihiko
AU - Ishida, Akio
AU - Komori, Akio
AU - Matsukawa, Makoto
AU - Motojima, Osamu
AU - Ogawa, Yuichi
AU - Ohno, Noriyasu
AU - Ono, Yasushi
AU - Peng, Martin
AU - Sudo, Shigeru
AU - Yamada, Hiroshi
AU - Yoshida, Naoaki
AU - Yoshida, Zensho
N1 - Publisher Copyright:
© 2010 The Japan Society of Plasma Science and Nuclear Fusion Research.
Copyright:
Copyright 2017 Elsevier B.V., All rights reserved.
PY - 2010
Y1 - 2010
N2 - QUEST focuses on the steady state operation of the spherical tokamak by controlled PWI and electron Bernstein wave current drive. One of the main purposes of QUEST is an achievement of long duration discharge with MW-class injected power. As the result, QUEST should be operated in the challenging region on heat and particle handling. To do the particle handling, high temperature all metal wall up to 623K and closed divertors are planned, which is to realize the steady-state operation under recycling ratio, R = 1. This is a dispensable check to DEMO, because wall pumping should be avoided as possible in the view of tritium retention. The QUEST project will be developed in increment step such as, I. low β steady state operation in limiter configuration, II. low β steady state operation in divertor configuration, III. relatively high β steady state operation in closed divertor configuration. Phase I in the project corresponds to these two years, and final goal of phase I is to make full current drive plasma up to 20 kA. Closed divertor will be designed and tested in the Phase II. QUEST is running from Oct., 2008 and the first results are introduced.
AB - QUEST focuses on the steady state operation of the spherical tokamak by controlled PWI and electron Bernstein wave current drive. One of the main purposes of QUEST is an achievement of long duration discharge with MW-class injected power. As the result, QUEST should be operated in the challenging region on heat and particle handling. To do the particle handling, high temperature all metal wall up to 623K and closed divertors are planned, which is to realize the steady-state operation under recycling ratio, R = 1. This is a dispensable check to DEMO, because wall pumping should be avoided as possible in the view of tritium retention. The QUEST project will be developed in increment step such as, I. low β steady state operation in limiter configuration, II. low β steady state operation in divertor configuration, III. relatively high β steady state operation in closed divertor configuration. Phase I in the project corresponds to these two years, and final goal of phase I is to make full current drive plasma up to 20 kA. Closed divertor will be designed and tested in the Phase II. QUEST is running from Oct., 2008 and the first results are introduced.
KW - Electron Bernstein wave
KW - Plasma wall interaction
KW - Spherical tokamak
KW - Steady state operation
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U2 - 10.1585/pfr.5.S1007
DO - 10.1585/pfr.5.S1007
M3 - Article
AN - SCOPUS:80054834145
VL - 5
JO - Plasma and Fusion Research
JF - Plasma and Fusion Research
SN - 1880-6821
M1 - S1007
ER -