تاثیر پلاسما، آهن ربا و عملکرد دیواره در توکامک و اقتصاد راکتور مارپیچ
|کد مقاله||سال انتشار||تعداد صفحات مقاله انگلیسی||ترجمه فارسی|
|11332||2006||5 صفحه PDF||سفارش دهید|
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Publisher : Elsevier - Science Direct (الزویر - ساینس دایرکت)
Journal : Fusion Engineering and Design, Volume 81, Issues 8–14, February 2006, Pages 1145–1149
For the assessment of both tokamak and helical reactors, the base case reactor models are introduced, and parameter scan analyses on plasma beta, electric power output, maximum magnetic field strength and neutron wall loading are carried out. The assessment shows that high temperature operation is appropriate in tokamak reactors to increase bootstrap current fraction and current-drive (CD) efficiency. In contrast, low-temperature high-density operation is feasible and desirable in helical system to reduce helical ripple transport. The capital cost of helical reactors is rather high; however, the cost of electricity (COE) is not much higher than that of tokamak reactors especially in the case of low beta design, because of smaller re-circulation power (no current-drive power) and less-frequent blanket replacements due to lower neutron wall load. The engineering improvement of increasing maximum magnetic field strength gives rise to the compact designs with lower construction cost. However, it does not lead to the strong reduction in COE because of the increase in the neutron wall loading. The COE critically depends on the system availability which is determined by the wall lifetime and the blanket maintenance time.
For the realization of attractive fusion power plants we need high-beta, good-confinement, steady-state plasma characteristics and high-field, high-wall-load, efficient-blanket engineering performances. The tokamak system has better plasma confinement properties; however, the current-drive re-circulation power and the plasma current disruption events are problematic. In contrast, the helical system is expected as a steady-state reactor, but a rather big and expensive system should be improved. To search for a favorable toroidal fusion reactor, we have evaluated fusion reactor economics using the physics–engineering–cost (PEC) code ,  and . Its assessment models and comparative results for both tokamak and stellarator systems are reported here.