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