DocumentCode
2937535
Title
Progress in the design of the ITER divertor maintenance system
Author
Martin, E. ; Maisonnier, D. ; Tada, E. ; Blevins, J. ; Burgess, T. ; Cerdan, G. ; Chioccio, S. ; Damiani, C. ; Duglué, D. ; Janeschitz, G. ; Shibanuma, K. ; Sironi, M. ; Tesini, A. ; Tivey, R.
Author_Institution
Garching Joint Work Site, ITER Joint Central Team, Germany
Volume
2
fYear
1997
fDate
6-10 Oct 1997
Firstpage
965
Abstract
The remote installation of the ITER divertor, based on 2 in-vessel concentric toroidal rails and 4 radial rails, has been reported. This paper concentrates on the design developed for handling equipment through the divertor RH ports. It reviews the progress made towards the establishment of a full scale facility to develop and demonstrate the divertor remote maintenance. Moreover, it reports on the preliminary maintenance scheme of the divertor diagnostics and cryopumps
Keywords
Tokamak devices; cryopumping; fusion reactor design; nuclear reactor maintenance; ITER; cryopumps; diagnostics; divertor; divertor RH ports; maintenance system; remote maintenance; Chromium; Circuits; Cooling; Ducts; Inductors; Plugs; Rails; Research and development; Testing; Vacuum systems;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location
San Diego, CA
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687785
Filename
687785
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