Observed modes of DIII-D divertor operation and the corresponding strike point locations at the lower divertor
In order to study the effects of plasma erosion and redeposition in a tokamak operating with a divertor, twelve graphite tiles, the surface of which were well characterized by profilometry, have been installed into the lower divertor region of the DIII-D tokamak. This experiment is the first phase of the DIII-D Erosion Study, a collaborative effort involving General Atomics, Lawrence Livermore National Laboratory, Argonne National Laboratory, and Sandia National Laboratory-Livermore. After an exposure of approximately none calendar months, the tiles are to be removed and the surface profiles precisely measured at Sandia, to determine the location and magnitude of the erosion and redeposition of tile material. An additional aim of the Erosion Study is to assist in benchmarking the REDEP code being developed by Jeff Brooks at Argonne National Laboratory to calculate the net erosion and redeposition of materials exposed to magnetically confined plasmas. The REDEP code has been used extensively to predict the performance of divertors in planned fusion reactors such as ITER, and although the code has been benchmarked to TFTR limiter measurements, a comparison is needed with direct erosion measurements of diverter plate material. This paper will summarize the relevant experimental data, their availability to users of the GA VAX cluster, and the procedure used to characterize the operation of DIII-D. More detailed descriptions of the commands used with the various codes are provided in the appendix.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- AC03-89ER52153
- OSTI ID:
- 720092
- Report Number(s):
- GA-C--19821; ON: TI90020196
- Country of Publication:
- United States
- Language:
- English
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