Tritium transport in the water cooled Pb17Li blanket concept of DEMO
- 1 January 1991
- journal article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 15 (3) , 223-234
- https://doi.org/10.1016/0920-3796(92)90041-2
Abstract
No abstract availableKeywords
This publication has 6 references indexed in Scilit:
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- Hydrogen transport and solubility in 316L and 1.4914 steels for fusion reactor applicationsJournal of Nuclear Materials, 1988
- Tritium-material interaction in various first wall materialsJournal of Nuclear Materials, 1988
- Interaction of Hydrogen Isotopes with Stainless Steel 316 LFusion Technology, 1985
- A calculation of the surface recombination rate constant for hydrogen isotopes on metalsJournal of Nuclear Materials, 1980