PRELIMINARY STUDY OF PLASMA PARTICLE CONFINEMENT AND POWER BALANCE IN FUSION REACTOR

• Main Author: KURNIA (NIM 10205060), FRAN
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/10465
• Institution: Institut Teknologi Bandung

The analysis of particle excursion in the effect of magnetic field confinement and its energy loss has been performed. The analysis use MATLAB tools in order to display gradient of both toroidal and poloidal magnetic confinement. 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 MS-Excel. 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. The benchmarking is based on parameter reactor research design that has been performed previously, which is built in U.K., Japan, and the U.S. The gradient of magnetic confinement follows the direction of magnetic field line. It means that particle will move by the same direction as the magnetic field direction, but in most cases there will always be particle excursion displacement from the expected result. The value of particle excursion displacement in ITER design is about 1.85 cm in assumption of the particle is marginally trapped in reactor chamber. In Joint European Torus (JET) design, this value is around 3.95 cm. Another design comes from Japan, it is named JT-60 design, and with particle excursion displacement is about 1.7 cm. In ITER design, one generates the initial value of toroidal magnetic field is about 5.3 T with 837 m3 of plasma volume, and in JET design, the initial toroidal magnetic field value is only about 3.4 T with 540m3 of plasma volume, whereas in JT-60 design, one generates only 2.68 T toroidal magnetic field with 127 m3 plasma volume. 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. <br />