Tritium inventory and recovery for a self-cooled PbLi blanket
- 1 April 1991
- journal article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 14 (3-4), 413-425
- https://doi.org/10.1016/0920-3796(91)90022-i
Abstract
No abstract availableKeywords
This publication has 6 references indexed in Scilit:
- Self-cooled blanket concepts using Pb7Li as liquid breeder and coolantFusion Engineering and Design, 1991
- Tritium inventory and permeation in separately cooled liquid breeder blanketsJournal of Nuclear Materials, 1989
- The use of aluminising on 317 austenitic and 1.4914 martensitic steels for the reduction of tritium leakage from the net blanketJournal of Nuclear Materials, 1989
- The role of a blanket tritium system on the fusion fuel cycleFusion Engineering and Design, 1989
- Hydrogen transport and solubility in 316L and 1.4914 steels for fusion reactor applicationsJournal of Nuclear Materials, 1988
- Effectiveness of Tritium Removal from a CTR Lithium Blanket by Cold Trapping Secondary Liquid Metals Na, K, and NaKNuclear Technology, 1974