New project: HT-7UObjective• Investigation and developing of the engineeringand technology of a full superconducding tokamak• Steady-state operation with higher plasma performance;• Investigation of Advanced Tokamak physics;• Power and particle handle under steady-state
operation condition
Prepare to go to SS/AT reactor

Typical magnetic configuration and divertor design
Z(cm)

Z(cm)
PF9PF7PF7PF9TF coil
PF11PF5PF3PF3PF1PF1PF2PF2PF4PF4PF8PF12PF6PF12PF6PF11PF5PF8PF10PF10R(cm)

cm

R(cm)

Z (cm)PF7PF5PF9PF7PF11PF3PF1PF1PF2PF2PF4PF4PF8PF11PF5PF3PF6PF9PF12PF6PF12PF8PF10cm

PF10R (cmNational research project

HT-7U superconducting tokamak

Engineering design
HT-7U Tokamak

Main Parameters
Toroidal Field, Bo
3.5 T
Plasma Current, IP 1 MA
Major Radius, Ro 1.7 m
Minor Radius, a0.4 m
Aspect Ratio, R/a
4.25
1.6 - 2Elongation, Kx
Triangularity, d x 0.6 - 0.8
Heating andCurrent Driving:
ICRH
3 - 3.5 MW
LHCD
3.5 MW
ECRH
0.5 MW
Pulse length
1000 sFirst wall materials (1)First wall material tests(2)Superconducting Magnet Test Facility(1)Superconducting Magnet Test Facility.(2)New project: HT-7UObjective• Investigation and developing of the engineeringand technology of a full superconducding tokamak• Steady-state operation with higher plasma performance;• Investigation of Advanced Tokamak physics;• Power and particle handle under steady-state
operation condition
Prepare to go to SS/AT reactor

Typical magnetic configuration and divertor design
Z(cm)

Z(cm)
PF9PF7PF7PF9TF coil
PF11PF5PF3PF3PF1PF1PF2PF2PF4PF4PF8PF12PF6PF12PF6PF11PF5PF8PF10PF10R(cm)cm

R(cm)

Z (cm)PF7PF5PF9PF7PF11PF3PF1PF1PF2PF2PF4PF4PF8PF11PF5PF3PF6PF9PF12PF6PF12PF8PF10cm

PF10R (cmNational research project

HT-7U superconducting tokamak

Engineering design
HT-7U Tokamak

Main Parameters
Toroidal Field, Bo
3.5 T
Plasma Current, IP 1 MA
Major Radius, Ro 1.7 m
Minor Radius, a0.4 m
Aspect Ratio, R/a
4.25
1.6 - 2Elongation, Kx
Triangularity, d x 0.6 - 0.8
Heating andCurrent Driving:
ICRH
3 - 3.5 MW
LHCD
3.5 MW
ECRH
0.5 MW
Pulse length1000 s

First wall materials (1)First wall material tests(2)Superconducting Magnet Test Facility(1)Superconducting Magnet Test Facility.(2)The maximum current on CSMC achieved 13000A

CSMC sustained fast current dropThe cryostat, vacuum vessel, twothermal shields and support structure
system are fabricated in industrial
company and will be completed aroundmiddle of next year.

The building for HT-7U(will be completed around May 2002)¨ 1994~

Submitting the proposal and begin the conceptualphysics design¨ 1996

Begin the preliminary engineering design¨ 1997

The project approved by government andconceptual engineering design¨ 1998 -1999 Final conceptual engineering design and R&D¨ 2000 - 2001 Engineering design and begin fabrication¨ 2001 - 2002 Fabrication and some pre-assembly test
¨ 2002 - 2003 Fabrication and assembly¨ Around 2004 Complete assembly and hope to get first plasmaPossible future plan
will be proposedby fusion community in China• Participate ITER if it is possible and if ITER can beconstructed• Test reactor for breeding fission fuel and transmutation
the high radiation waste if both HL-2A and HT-7U
are fully success.

Summary• Magnetic confinement fusion research is getting more
support in China ;• The significant progresses from small to medium size andsuperconducting tokamak have been achieved;• China will certainly make more contribution to fusion
research after new projects to be completed;• Fusion community in China hopes that ITER can beconstructed finally and both SWIP and ASIPP will
promote to participate ITER project by a suitable way
for China if ITER can be constructed.