DocumentCode :
3170710
Title :
Design layout and maintenance of the ARIES-III tokamak reactor
Author :
Sharafat, S. ; Najmabadi, F. ; Sviatoslavsky, I.
fYear :
1991
fDate :
30 Sep-3 Oct 1991
Firstpage :
1039
Abstract :
The direct integration activities of the ARIES-III reactor study have resulted in a reactor component layout that minimizes the number of vacuum-vessel penetrations and the number of connect/disconnects, and allows divertor target maintenance without affecting other components. A bifurcated divertor pumping duct at the bottom of the machine serves as an access port to the lower divertor plate and also provides adequate room for performing connect/disconnect actions on the inboard and outboard shield modules. The upper divertor-plate piping network is elevated above the inboard shield, which gives access to any in-vessel component. Minor first-wall recoating can be performed in situ using remote-controlled plasma-spray equipment already in service. Access to the vacuum vessel form the top requires lifting the upper two poloidal-field coils with their cryostat and support structure
Keywords :
Tokamak devices; fusion reactor theory and design; nuclear reactor maintenance; ARIES-III reactor study; bifurcated divertor pumping duct; direct integration activities; divertor target maintenance; first-wall recoating; poloidal-field coils; reactor component layout; remote-controlled plasma-spray equipment; tokamak fusion reactor; upper divertor-plate piping network; vacuum-vessel penetrations; Ducts; Flexible printed circuits; Floors; Fusion reactor design; Inductors; Niobium; Pumps; Radio frequency; Superconducting coils; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
Type :
conf
DOI :
10.1109/FUSION.1991.218769
Filename :
218769
Link To Document :
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