DocumentCode :
3212482
Title :
Preliminary study of plasma particles confinement and power balance in fusion reactor device by using ITER simulation method
Author :
Kurnia, F. ; Su´ud, Z.
Author_Institution :
Nucl. Phys. Lab., Inst. Teknol., Bandung, Indonesia
fYear :
2009
fDate :
1-5 June 2009
Firstpage :
1
Lastpage :
1
Abstract :
Summary form only given. The analysis of particle excursion in the effect of both toroidal and poloidal magnetic field confinement and its energy loss has been performed. The other physical parameters such as, particle gyro radius, velocity, particle excursion, and the loss of energy rate in plasma are calculated numerically by using ITER simulation method. In order to verify the quality of another fusion reactor design, benchmarking to International Thermonuclear Experimental Reactor (ITER), the best design of fusion reactor on earth, has also been performed. This is based on parameter reactor research design that has been performed previously, which is built in U.K. and Japan. The gradient in magnetic confinement region follows the direction of magnetic field curvature. It means that particle will move by the same direction as the magnetic field, but in most cases there will always be particle excursion from the expected result. The magnitude of particle displacement in ITER design is around 1.85 cm in which assumes of the particle is marginally trapped in reactor chamber. In another design, Joint European Torus (JET), this value is around 3.95 cm, whereas the other design comes from Japan, it is named JT-60, in which particle excursion circa 1.7 cm. Almost all of the TOKAMAK design, there is a continuous loss of energy from the plasma which has to be replenished by plasma heating. Its value is depending inversely on the time confinement of plasma. All of the result just represents the simplified Large TOKAMAK model that is used in order to design the plasma fusion reactor by using ITER simulation method.
Keywords :
Tokamak devices; fusion reactor design; plasma simulation; plasma toroidal confinement; ITER simulation method; International Thermonuclear Experimental Reactor; JT-60; Joint European Torus; Large TOKAMAK model; energy loss; fusion reactor design; fusion reactor device; particle excursion; plasma heating; plasma particles confinement; poloidal magnetic field confinement; power balance; toroidal magnetic field confinement; Fusion reactor design; Fusion reactors; Inductors; Magnetic analysis; Magnetic confinement; Plasma confinement; Plasma devices; Plasma simulation; Tokamaks; Toroidal magnetic fields;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Plasma Science - Abstracts, 2009. ICOPS 2009. IEEE International Conference on
Conference_Location :
San Diego, CA
ISSN :
0730-9244
Print_ISBN :
978-1-4244-2617-1
Type :
conf
DOI :
10.1109/PLASMA.2009.5227364
Filename :
5227364
Link To Document :
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