Fusion Device data - HT7

Title of DeviceHT-7, Hefei Tokamak-7
LocationHefei, China
A. Device concept and components
Concept tokamak
Vacuum vessel: -- Plasma facing material: stainless steel / ferretic steel [1][2]
Divertor/limiter facing material graphite [1]
Working Gas D [1]
Boundary configuration: limiter [1][2]
Toroidal magnetic field (on axis), B (T): 2T [1]
B. Plasma geometry
Major radius, R(m): 1.22 [1]
Minor radius, a(m): 0.27 [1]
Plasma volume (m3): ~1.7
C. Plasma parameters (maximum values)
Central ion temperature, Ti (keV): 1.5 [2]
Central electron temperature, Te (keV): 4 [3]
Line averaged plasma density, <n> (1020 m-3): 0.65 [1]
Central electron density, n (1020 m-3): 8
Plasma current, I (MA): 0.25 [1]
Discharge pulse duration (s): 50
Plasma beta, <β> (%): 0.5 [2]
Stored energy, (MJ): 0.025
Energy confinement time, τE (s): 0.029 [2]
D. Plasma heating and current drive (device values)
Ohmic heating, (MW):2 MW/MA
NBI heating, (MW):0(0.4) [3]
RF heating: -IC: (MW):0.35(1.5) [3]
RF heating: -EC: (MW):0(0.2) [3]
RF heating: -LH: (MW):1.2 [1]
E. Reactor relevant plasma performance parameters
Triple fusion product, ( 1020 keV s m-3): 0.01 [3]
QDT factor (if available):-
F. Input information
Date of entry 7-Mar-2003
Data was entered by: Baonian WAN