Community Research and Development Information Service - CORDIS


In this paper is presented a summary of recent DIII-D divertor physics activity and plans for future divertor upgrades. During the past year, DIII-D experimental effort focused on areas of active heat and particle control and divertor target erosion studies. Using the DIII-D advanced divertor system, control of the plasma density has been demonstrated. Divertor heat flux control by means of D(2) gas puffing and impurity injection were studied separately and in both cases up to a factor of five reduction of the divertor peak heat flux was observed. Using the DiMES sample transfer system, erosion data have been obtained on various material samples in well diagnosed plasmas. The results are compared with predictions of numerical models.

Additional information

Authors: MAHDAVI M A ET AL., Lawrence Livermore National Laboratory, San Diego (US)
Bibliographic Reference: Article: Journal of Nuclear Materials, Vol. 220-222 (1995) pp. 13-24
Record Number: 199510748 / Last updated on: 1995-07-12
Original language: en
Available languages: en