DocumentCode :
2554924
Title :
TPX in-vessel remote maintenance tooling
Author :
Rennich, M.J. ; Silke, G.W.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
Volume :
2
fYear :
1995
fDate :
30 Sep-5 Oct 1995
Firstpage :
1367
Abstract :
The Tokamak Physics Experiment (TPX) has used the lessons learned from successful remote maintenance and remote handling facilities to develop both a concept and philosophy for incorporation of remote design from the earliest phases of the project. Initiation of mockup testing during the conceptual design phase leads to significant improvements in the basic maintenance equipment configuration. In addition, remote handling features and capabilities have been incorporated into the design of the plasma-facing components (PFCs) as part of the total PFC design effort
Keywords :
Tokamak devices; fusion reactor operation; nuclear reactor maintenance; telecontrol; TPX in-vessel remote maintenance tooling; Tokamak Physics Experiment; basic maintenance equipment configuration; plasma-facing components; remote handling facilities; remote handling features; Fusion power generation; Laboratories; Physics; Plasma diagnostics; Rails; Remote handling; Testing; Tokamaks; Vehicles; Water pollution;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
Type :
conf
DOI :
10.1109/FUSION.1995.534482
Filename :
534482
Link To Document :
بازگشت