DocumentCode :
2722487
Title :
Development of high field pulse tokamak using force free coil concept for fusion reactor safety research
Author :
Miura, Yushi ; Shimada, Ryuichi
Author_Institution :
Res. Lab. for Nucl. Reactors, Tokyo Inst. of Technol., Japan
Volume :
1
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
353
Abstract :
The study of the fusion reactor safety using the real reactor relevant plasma to examine the safety is essential for meeting new energy having the potential of public acceptance. If we have a high magnetic field technology that is three times higher than the present day tokamak, it is easy predict using the resent experimental result that the very small tokamak can reach the reactor grade plasma. These supporting experimental machines are important for the fusion reactor development to add the review method for safety and environmental view points. To obtain ultra-high field, the force free coil concept is developed. This force balanced coil (FBC) idea has a possibility to get higher field by canceling magnetic forces themselves. The magnetic configuration near plasma is tokamak-like one by using the multi-helical windings. The difference from ordinary tokamak is that the coils generate the toroidal and poloidal field all together and they ramp up with plasma current. Thus, this device needs the special operation to break down and ramp up phase of plasma. In this paper the high field ramp-up tokamak for fusion reactor safety research is proposed, and the feasibility applying the single layered multi-helical force balanced coil to tokamak is investigated with consideration to plasma confinement. The scenario to the nuclear burning phase in a pulse operation is simulated including the effect of the increase of the toroidal field with plasma current
Keywords :
Tokamak devices; fusion reactor design; fusion reactor safety; break down; force balanced coil; force free coil concept; fusion reactor safety research; high field pulse tokamak; magnetic configuration; magnetic force cancellation; multi-helical windings; nuclear burning phase; plasma confinement; plasma current ramp up; poloidal field generation; reactor grade plasma; real reactor relevant plasma; single layered multi-helical force; toroidal field; toroidal field generation; ultra-high field; Coils; Fusion reactors; Inductors; Plasma confinement; Plasma devices; Plasma simulation; Potential energy; Safety; Tokamaks; Toroidal magnetic fields;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
Type :
conf
DOI :
10.1109/FUSION.1993.518348
Filename :
518348
Link To Document :
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