Title :
Engineering design of a radiative divertor for DIII-D
Author :
Smith, J.P. ; Baxi, C.B. ; Bozek, A.S. ; Chin, E. ; Hollerbach, M.A. ; Johnson, W.R. ; Laughon, G.J. ; Phelps, R.D. ; Redler, K.M. ; Reis, E.E. ; Sevier, D.L.
Author_Institution :
Gen. Atomics, San Diego, CA, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
A new divertor configuration is being developed for the DIII-D tokamak. This divertor will operate in the radiative mode. Experiments and modeling form the basis for the new design. The radiative divertor reduces the heat flux on the divertor plates by dispersing the power with radiation in the divertor region. In addition, the radiative divertor structure will allow density control in plasma shapes required for advanced tokamak operation. The divertor structure allows for operation in either double-null or single-null plasma configurations. Four independently controlled divertor cryopumps will enable pumping at either the inboard (upper and lower) or the outboard (upper and lower) divertor plates. An upgrade to the DIII-D cryogenic system is part of this project. The increased capabilities of the cryogenic system will allow delivery of liquid helium and nitrogen to the three new cryopumps. The radiative divertor design is very flexible, and will allow physics studies of the effects of slot width and length. The slot width is varied by installing graphite tiles of different geometry and can be accomplished in a shut down of less than 3 weeks. The change in slot length requires moving the structure vertically and could to be done in about 6-8 weeks. Slot lengths of 23, 33, and 43 cm have been chosen. Radiative divertor diagnostics are being designed in parallel to provide comprehensive measurements for diagnosing the divertor. The radiative divertor installation is scheduled for late 1996. Engineering experience gained in the DIII-D advanced divertor program form a foundation for the design work on the radiative divertor
Keywords :
cryogenics; cryopumping; fusion reactor design; fusion reactor operation; fusion reactors; plasma density; plasma diagnostics; plasma toroidal confinement; 23 cm; 33 cm; 43 cm; 6 to 8 week; C; DIII-D tokamak; He; N; advanced tokamak operation; cryogenic system; density control; divertor diagnostics; double-null configurations; engineering design; fusion reactor; graphite tiles; independently controlled divertor cryopumps; plasma shapes; radiative divertor; single-null plasma configurations; slot width; Cryogenics; Design engineering; Geometry; Helium; Nitrogen; Physics; Plasma density; Shape control; Tiles; Tokamaks;
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
DOI :
10.1109/FUSION.1995.535955