DocumentCode :
298256
Title :
Design layout and maintenance of the ARIES-IV tokamak fusion power plant
Author :
Sharafat, S. ; Junge, R. ; Najmabadi, F. ; Sviatoslavsky, I. ; Wong, C.P.C.
Author_Institution :
Dept. of Mech., Aerosp. & Nucl. Eng., California Univ., Los Angeles, CA, USA
Volume :
1
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
417
Abstract :
The ARIES-IV fusion power plant is a conceptual, steady-state, D-T burning, 1000-MWe net-power tokamak, operating in the second-stability plasma regime. Design simplicity, maintainability, and reasonable maintenance downtimes are crucial for viable and competitive fusion economics. The ARIES-IV design team developed a maintenance scheme that allows rapid and simultaneous replacement of all of the components in a large, self-contained fusion-power-core (FPC) section. The FPC is divided into 16 self-contained “pie-shaped” sections that can be removed horizontally through large vacuum-vessel access ports located between the outer legs of the toroidal-field (TF) coils. Prior to commitment to service, the entire FPC section assembly is pretested extensively to maximize operating reliability. To facilitate this radial section-removal scheme, the TF coils and the poloidal-field (PF) coils of the ARIES-IV tokamak had to be enlarged. The advantages of the ARIES-IV section-replacement scheme over more traditional approaches, where individual FPC components are removed sequentially from the vacuum vessel, outweigh the cost increases associated with larger TF- and PF-coil systems
Keywords :
economics; fusion reactor design; fusion reactor operation; nuclear power stations; nuclear reactor maintenance; plasma instability; plasma toroidal confinement; power system reliability; 1000 MW; ARIES-IV tokamak fusion power plant; DT; conceptual steady-state tokamak; design layout; fusion economics; maintenance downtimes; operating reliability; poloidal-field coils; radial section-removal scheme; rapid replacement; second-stability plasma regime; self-contained fusion-power-core; self-contained pie-shaped sections; simultaneous replacement; toroidal-field coils; vacuum-vessel access ports; Assembly; Coils; Flexible printed circuits; Leg; Plasmas; Power generation; Power generation economics; Steady-state; Tokamaks; Vacuum systems;
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.1993.518362
Filename :
518362
Link To Document :
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