Fusion Device data - HT7U

Title of DeviceHT-7U (EAST) [2]
OrganizationInstitute of Plasma Physics, Chinese Academy of Sciences
LocationHefei, China
A. Device concept and components
Concept tokamak
Vacuum vessel: -- Plasma facing material: stainless steel
Divertor/limiter facing material carbon [1]
Working Gas H / D [1]
Boundary configuration: diverter [1]
Toroidal magnetic field (on axis), B (T): 3.5 [1], 4 in the second phase [2]
B. Plasma geometry
Major radius, R(m): 1.75 [1]
Minor radius, a(m): 0.4 [1]
Plasma volume (m3): -
C. Plasma parameters (maximum values)
Central ion temperature, Ti (keV): -
Central electron temperature, Te (keV): -
Line averaged plasma density, <n> (1020 m-3): -
Central electron density, n (1020 m-3): -
Plasma current, I (MA): 1 [1], 1.5 in the second phase
Discharge pulse duration (s): 1000 [1]
Plasma beta, <β> (%): 1 [2], 1.2 in the second phase
Stored energy, (MJ): 0.77[2], 1.2 in the second phase
Energy confinement time, τE (s): 0.127 [2], 0.2 [2] in the second phase
Remarks:performance evaluation with H89~2 in D plasma from design [2]
D. Plasma heating and current drive (device values)
Ohmic heating, (MW):1 MW/MA
NBI heating, (MW):4-8 in the second phase [2]
RF heating: -IC: (MW):3 [1][2] in the first phase
RF heating: -EC: (MW):0.5 [1][2] in the first phase
RF heating: -LH: (MW):3.5 [1][2] in the first phase
E. Reactor relevant plasma performance parameters
Triple fusion product, ( 1020 keV s m-3): 0.4 [2], 0.9 in the second phase [2]
QDT factor (if available):-
F. Input information
Date of entry 14-Mar-2003
Data was entered by: Baonian WAN