Divertor heat and particle control experiments on the DIII-D tokamakFunded under: EAEC-FUSION 12C
This paper presents a summary of a 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, it has been possible to control the plasma density and demonstrate helium exhaust in H-mode plasmas. 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. The DiMES sample transfer system provided erosion data on various material samples in well diagnosed plasmas and the results are compared with predictions from numerical models.
Bibliographic Reference: Article: Journal of Nuclear Materials, Vols. 220-222 (1995) pp. 13-24
Record Number: 199510892 / Last updated on: 1995-08-10
Original language: en
Available languages: en