Tritium retention in plasma facing components for NET/ITER fusion devices
- 1 December 1991
- journal article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 16, 393-405
- https://doi.org/10.1016/0920-3796(91)90215-c
Abstract
No abstract availableKeywords
This publication has 15 references indexed in Scilit:
- Flux and fluence dependence of H+ trapping in graphiteJournal of Nuclear Materials, 1990
- Hydrogen trapping and transport in carbonJournal of Nuclear Materials, 1989
- The interaction of tritium with graphite and its impact on tokamak operationsJournal of Nuclear Materials, 1989
- Absorption and desorption of deuterium on graphite at elevated temperaturesJournal of Nuclear Materials, 1988
- Hydrogen recycling properties of graphiteJournal of Nuclear Materials, 1987
- Plasma-material interactions in TFTRJournal of Nuclear Materials, 1987
- Saturation and isotopic replacement of deuterium in low-z materialsJournal of Nuclear Materials, 1980
- Computer code peri for the calculation of recycling, volume distribution, and permeation of hydrogen in first wall materials of tokamaksJournal of Nuclear Materials, 1980
- Trapping of deuterium implanted in carbon and silicon: A calibration for particle-energy measurements in the plasma boundary of tokamaksJournal of Nuclear Materials, 1979
- Studies on ultra-clean carbon surfaces—III. Kinetics of chemisorption of hydrogen on graphonCarbon, 1971