Investigation of γ lithium aluminate as tritium breeding material for a fusion reactor blanket
Authors:
- J. CharpinJCJ. Charpin
- F. BotterFBF. Botter
- M. BriecMBM. Briec
- B. RasneurBRB. Rasneur
- E. RothERE. Roth
- N. RouxNRN. Roux
- J. SannierJSJ. Sannier
- 1 January 1989
- journal article
- Published by Elsevier in Fusion Engineering and Design
- Vol. 8, 407-413
Abstract
No abstract availableThis publication has 9 references indexed in Scilit:
- Irradiation behaviour of a tritium breeding material, γ-LiAlO2- results of two in-pile experiments: ALICE I and ALICE IIJournal of Nuclear Materials, 1988
- Compatibility of stainless steels and lithiated ceramics with berylliumJournal of Nuclear Materials, 1988
- In-pile tritium extraction from samples of lithium aluminateJournal of Nuclear Materials, 1988
- In-pile tritium release behavior from lithium aluminate and lithium orthosilicate of the VOM-23 experimentJournal of Nuclear Materials, 1988
- Investigation of the mechanical properties of ceramic breeder materialsJournal of Nuclear Materials, 1988
- Chemical properties of lithium ceramics: Reactivity with water and water vapourJournal of Nuclear Materials, 1988
- Effects of radiation on lithium aluminate samples propertiesJournal of Nuclear Materials, 1986
- Compatibility of 316L stainless steel with liquid and solid tritium breeding materialsJournal of Nuclear Materials, 1986
- Tritium Breeding Material :γ LiAlO2Fusion Technology, 1985