DocumentCode
298228
Title
TPX divertor design for remote handling
Author
Anderson, P.M.
Author_Institution
Gen. Atomics, San Diego, CA, USA
Volume
1
fYear
1993
fDate
11-15 Oct 1993
Firstpage
286
Abstract
The TPX tokamak incorporates a double null slot divertor that may be operated in a single or double null mode. Each divertor consists of separate heat flux panels for the inner, baffle, and outer divertor. Provisions are incorporated to provide for radiative divertor operation to reduce the peak heat flux to the divertor. Particle pumping is provided through vertical ports to control the plasma density and density profile. The ORNL-developed in-vessel manipulator traverses the vessel toroidally on an upper and lower pair of circular tracks. Manipulator arms and/or a dedicated elevator system will position special end effecters which mate with the divertor modules. Each divertor system is comprised of 16 toroidal sectors of 22.5° each. A set of mounting rings are used for mechanical attachment of the modules to the vessel. Mechanical attachments to these mounting rings are made with clamping nut/bolt systems. The nuts and bolts are captive to the divertor modules allowing for inspection and cleaning or repair of all fastener threads when the module is removed from the vacuum vessel. Several remote tools are required for divertor remote installation and removal. These tools include: two end effectors to interface with the divertor modules; bolt torquing tools; an internal pipe cutter for remote severing of 5 in. titanium pipe; an internal welder for remote welding of 5 in. diameter titanium pipe. Each of the 64 divertor modules incorporates a remotely engaged electrical and multi-port pneumatic connector
Keywords
Tokamak devices; fusion reactor design; fusion reactor operation; fusion reactors; inspection; manipulators; plasma density; plasma toroidal confinement; telerobotics; 5 in; TPX divertor design; TPX tokamak; Ti; circular tracks; clamping nut/bolt systems; density profile control; double mode; double slot divertor; elevator system; end effecters; fusion reactor; in-vessel manipulator; inspection; mechanical attachment; peak heat flux; plasma density control; radiative divertor operation; remote handling; remote installation; repair; single mode; toroidal sectors; vacuum vessel; Arm; Clamps; Elevators; Fasteners; Manipulators; Plasma density; Remote handling; Titanium; Tokamaks; Welding;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location
Hyannis, MA
Print_ISBN
0-7803-1412-3
Type
conf
DOI
10.1109/FUSION.1993.518332
Filename
518332
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