1. Helium cooled ceramic breeder in tube blanket for a tokamak reactor: the coaxial poloidal module concept design;Anzidei,1989
2. Investigation of γ lithium aluminate as tritium breeding material for a Fusion Reactor Blanket;Charpin;Fusion Engineering and Design,1989
3. The ENEA selected fabrication process of γ-LiAlO2 ceramic pellets for tritium breeding experiments in Fusion Technology;Alvani,1987
4. Fabrication and characterization of γ-LiAlO2 and Li2ZrO3 ceramic breeder pellets for irradiation and blanket engineering experiments;Alvani,1991
5. Material data base for NET test Blanket design studies;Küchle,1988