Abstract
In this paper we present a summary of recent DIII-D divertor physics activity and plans for future divertor upgrades. During the past year, DIII-D experimental effort was focused on areas of active heat and particle control and divertor target erosion studies. Using the DIII-D Advanced Divertor system we have succeeded for the first time to control the plasma density and demonstrate helium exhaust in H-mode plasmas. Divertor heat flux control by means of D2 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 we have obtained erosion data on various material samples in well diagnosed plasmas and compared the results with predictions of numerical models.
Original language | English |
---|---|
Pages (from-to) | 13-24 |
Number of pages | 12 |
Journal | Journal of Nuclear Materials |
Volume | 220-222 |
DOIs | |
State | Published - 1995 |
Externally published | Yes |
Funding
Development of an effective divertor heat control technique is essential for viability of ITER and other future tokamak fusion reactors. For example, ITER is expected to generate > 300 MW of alpha power. Such a large heat load is a severe technical challenge, espe- * Work supported by the US, Department of Energy under Contract nos. De-AC03-89ER51114, W-7405-ENG-48, DE-AC05-84OR21400, DE-FG03-89ER51121, and DE-AC03-76DP00789. 1 Lawrence Livermore National Laboratory. 2 Sandia National Laboratories. 3 University of California at Berkeley.
Funders | Funder number |
---|---|
U.S. Department of Energy | DE-FG03-89ER51121, De-AC03-89ER51114, W-7405-ENG-48, DE-AC03-76DP00789, DE-AC05-84OR21400 |
U.S. Department of Energy |