TY - JOUR
T1 - Formation of Advanced Tokamak Plasmas without the Use of an Ohmic-Heating Solenoid
AU - Shiraiwa, S.
AU - Ide, S.
AU - Itoh, S.
AU - Mitarai, O.
AU - Naito, O.
AU - Ozeki, T.
AU - Sakamoto, Y.
AU - Suzuki, T.
AU - Takase, Y.
AU - Tanaka, S.
AU - Taniguchi, T.
AU - Aramasu, M.
AU - Fujita, T.
AU - Fukuda, T.
AU - Gao, X.
AU - Gryaznevich, M.
AU - Hanada, K.
AU - Jotaki, E.
AU - Kamada, Y.
AU - Maekawa, T.
AU - Miura, Y.
AU - Nakamura, K.
AU - Nishi, T.
AU - Tanaka, H.
AU - Ushigusa, K.
PY - 2004
Y1 - 2004
N2 - A new operational scenario of advanced tokamak formation was demonstrated in the JT-60U tokamak. This was accomplished by electron cyclotron and lower hybrid waves, neutral beam injection, and the loop voltage supplied by the vertical field and shaping coils. The Ohmic heating (OH) solenoid was not used but a small inboard coil (part of the shaping coil), providing less than [Formula presented] of total poloidal flux, was used. The plasma thus obtained had both internal and edge transport barriers, with an energy confinement time of 1.6 times H-mode scaling, a poloidal beta of 3.6, and a normalized beta of 1.6, and a large bootstrap current fraction ([Formula presented]). This result opens up a possibility to reduce, and eventually eliminate, the OH solenoid from a tokamak reactor, which will greatly improve its economic competitiveness.
AB - A new operational scenario of advanced tokamak formation was demonstrated in the JT-60U tokamak. This was accomplished by electron cyclotron and lower hybrid waves, neutral beam injection, and the loop voltage supplied by the vertical field and shaping coils. The Ohmic heating (OH) solenoid was not used but a small inboard coil (part of the shaping coil), providing less than [Formula presented] of total poloidal flux, was used. The plasma thus obtained had both internal and edge transport barriers, with an energy confinement time of 1.6 times H-mode scaling, a poloidal beta of 3.6, and a normalized beta of 1.6, and a large bootstrap current fraction ([Formula presented]). This result opens up a possibility to reduce, and eventually eliminate, the OH solenoid from a tokamak reactor, which will greatly improve its economic competitiveness.
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U2 - 10.1103/PhysRevLett.92.035001
DO - 10.1103/PhysRevLett.92.035001
M3 - Article
AN - SCOPUS:84864767748
VL - 92
SP - 4
JO - Physical Review Letters
JF - Physical Review Letters
SN - 0031-9007
IS - 3
ER -