Modelling of the interaction of hydrogen plasma with amorphous carbon films redeposited in fusion devices
- 31 December 1993
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 207, 62-85
- https://doi.org/10.1016/0022-3115(93)90248-w
Abstract
No abstract availableKeywords
This publication has 92 references indexed in Scilit:
- Tritium release from a codeposited layer of carbon and tritium during air exposureJournal of Vacuum Science & Technology A, 1989
- Carbon deposition in the gaps between tiles: Data from the Tokamak Fusion Test Reactor and laboratory simulation studiesJournal of Vacuum Science & Technology A, 1989
- Hydrogen trapping and transport in carbonJournal of Nuclear Materials, 1989
- First-wall conditioning for enhanced confinement discharges and the DT experiments in TFTRJournal of Nuclear Materials, 1989
- The interaction of tritium with graphite and its impact on tokamak operationsJournal of Nuclear Materials, 1989
- Deposition of carbon, deuterium, and metals on the wall and limiters of the Tokamak Fusion Test ReactorJournal of Vacuum Science & Technology A, 1988
- Retention of hydrogen in graphiteJournal of Vacuum Science & Technology A, 1987
- Pumping of hydrogen during plasma–graphite interactionJournal of Vacuum Science & Technology A, 1987
- Hydrogen recycling properties of graphiteJournal of Nuclear Materials, 1987
- Surface analysis of 1984/85 Tokamak Fusion Test Reactor limiter tilesJournal of Vacuum Science & Technology A, 1986