DocumentCode
2552570
Title
Tokamak Physics Experiment divertor design
Author
Anderson, P.M.
Author_Institution
Gen. Atomics, San Diego, CA, USA
Volume
2
fYear
1995
fDate
30 Sep-5 Oct 1995
Firstpage
1262
Abstract
The Tokamak Physics Experiment (TPX) tokamak requires a symmetric up/down double-null divertor capable of operation with steady-state heat flux as high as 7.5 MW/m2. The divertor is designed to operate in the radiative mode and employs a deep slot configuration with gas puffing lines to enhance radiative divertor operation. Pumping is provided by cryopumps that pump through eight vertical ports in the floor and ceiling of the vessel. The plasma facing surface is made of carbon-carbon composite blocks (macroblocks) bonded to multiple parallel copper tubes oriented vertically. Water flowing at 6 m/s is used, with the critical heat flux (CHF) margin improved by the use of enhanced heat transfer surfaces. In order to extend the operating period where hands on maintenance is allowed and to also reduce dismantling and disposal costs, the TPX design emphasizes the use of low activation materials. The primary materials used in the divertor are titanium, copper, and carbon-carbon composite. The low activation material selection and the planned physics operation will allow personnel access into the vacuum vessel for the first 2 years of operation. This 2-year period will allow final in-vessel checkout of the remote handling equipment. The remote handling system requires that all plasma facing components (PFCs) are configured as modular components of restricted dimensions with special provisions for lifting, alignment, mounting, attachment, and connection of cooling lines, and instrumentation and diagnostics services. Alignment of the plasma facing surface to the as-built magnetic field and to neighboring modules is critical to limit peak temperatures and limit carbon impurities in the plasma. Both local edge-to-edge and overall alignment of the divertor is accomplished using a machined alignment ring system. This ring system maintains the modules in a circular array and is adjusted during machine assembly to align with the as-built magnetic field. The macroblocks have 10 mm of carbon-carbon protection for the copper tubes, of which 7 mm is considered erosion allowance
Keywords
Tokamak devices; fusion reactor design; fusion reactor materials; fusion reactors; C-C; Cu; Ti; Tokamak Physics Experiment divertor design; carbon impurities; carbon-carbon composite; carbon-carbon composite blocks; cryopumps; deep slot configuration; diagnostics services; enhanced heat transfer surfaces; erosion allowance; gas puffing lines; in-vessel checkout; instrumentation; low activation materials; macroblocks; multiple parallel copper tubes; plasma facing surface; radiative mode; remote handling equipment; remote handling system; steady-state heat flux; symmetric up/down double-null divertor; titanium; Copper; Floors; Heat transfer; Magnetic fields; Physics; Plasma diagnostics; Plasma temperature; Steady-state; Tokamaks; Water heating;
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.1995.534456
Filename
534456
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