DocumentCode
3172320
Title
Fabrication and test of hydraulic jacks for the application to divertor support system of Fusion Experimental Reactor
Author
Fukushima, H. ; Itoh, K. ; Ohmori, J. ; Miki, N. ; Tachikawa, N. ; Nishio, S. ; Koizumi, K. ; Okazaki, T. ; Shimizu, K.
Author_Institution
Heavy Apparatus Eng. Lab., Toshiba Corp., Yokohama, Japan
fYear
1991
fDate
30 Sep-3 Oct 1991
Firstpage
580
Abstract
Two different types of hydraulic jacks, consisting of hydraulic piston and bellows were developed for an application to locking and lifting systems for divertor segments for the Fusion Experimental Reactor. For the lifting system where a minimum stroke of 170 mm was required, a telescopic-type hydraulic jack with a length of 300 mm was fabricated and tested under an operation pressure of 1 MPa. For the locking system, a hydraulic jack with a conical cotter was developed that worked at 6.5 MPa under a radial offset of 2 mm. These jacks satisfied their specifications without any leakage, failure, or abrasion. The performance of several hard facing materials for the cotter, including alumina and metal alloys, was also examined. The Colmonoy No. 5 or Stellite alloy No. 6 was found to be excellent as a hard facing material for the cotter
Keywords
Tokamak devices; fusion reactor theory and design; Colmonoy; FER; Fusion Experimental Reactor; Stellite; alumina; bellows; conical cotter; divertor segments; hard facing materials; hydraulic jacks; hydraulic piston; locking system; metal alloys; Bellows; Fabrication; Fatigue; Inductors; Inorganic materials; Joining processes; Lifting equipment; Pistons; System testing; Welding;
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.1991.218854
Filename
218854
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