Speaker
Dr
JYOTIRMOY PRAMANIK
(DEPT OF PHYSICS, KHARAGPUR COLLEGE)
Description
Most of the tokamaks including ITER, a significant part of the plasma-facing component including diverters, limiters, etc is comprised with graphite material. In the fusion plasma environment, the graphite gets bombarded by hydrogen and its isotope (deuterium and tritium) ions and erode graphite to a significant extent. Since such carbon particles can retain large amounts of hydrogen, dust contributes to the problem of inventory of radioactive tritium inside the fusion machine. Another impact of the dust particles in the operation of a fusion device is the possible degradation of the discharge performance. Such particles penetrating in the core plasma region can lead to discharge disruption. Thus, in order to perform successful fusion experiments it is important to assess and understand the processes by which dust is formed and by which it interacts with the fusion device and its plasma. Instead of understanding processes that exactly happen inside a fusion reactor, it is always better to match some aspects of graphite-hydrogen interaction in a plasma environment in small laboratory devices, and study the physical processes. To address some of this issues, we have performed an experiment to examine the particle growth and sputtering yields in a DC glow discharge plasma in between the graphite electrodes.
| Country or International Organization | India |
|---|---|
| Paper Number | EX/P2-9 |
Primary author
Dr
JYOTIRMOY PRAMANIK
(DEPT OF PHYSICS, KHARAGPUR COLLEGE)
Co-authors
Mr
Pankaj Patra
(Dept of Physics, Kharagpur College, Kharagpur - 721305)
Dr
Pintu Bandyopadhyay
(Institute for Plasma Research,Gandhinagar - 382428)
