Author/Authors :
Kapychev، نويسنده , , V and Davydov، نويسنده , , D and Gorokhov، نويسنده , , Ioltukhovskiy، نويسنده , , A and Kazennov، نويسنده , , Yu and Tebus، نويسنده , , V and Frolov، نويسنده , , V and Shikov، نويسنده , , A and Shishkov، نويسنده , , N and Kovalenko، نويسنده , , V and Shishkin، نويسنده , , N and Strebkov، نويسنده , , Yu، نويسنده ,
Abstract :
This paper surveys the modules and materials of blanket tritium-breeding zones developed in the Russian Federation for fusion reactors. Synthesis of lithium orthosilicate, metasilicate and aluminate, fabrication of ceramic pellets and pebbles and experimental reactor units are described. Results of tritium extraction kinetics under irradiation in a water–graphite reactor at a thermal neutron flux of 5×1013 neutron/(s cm2) are considered. At the present time, development and fabrication of lithium orthosilicate–beryllium modules of the tritium-breeding zone (TBZ), have been carried out within the framework of the ITER and DEMO projects. Two modules containing orthosilicate pellets, porous beryllium and beryllium pebbles are suggested for irradiation tests in the temperature range of 350–700°C. Technical problems associated with manufacturing of the modules are discussed.
