Research and development of lithium ceramics and models of tritium breeding zones for blankets in Russian reactor projects

摘要

Main results of in-pile reactor testing of the first model of the tritium breeding zones (TBZ) for fusion reactor blankets containing both lithium orthosilicate and beryllium spheroid particles are presented. Experimental results of tritium inflow - in the form of HT and HTO - into neon purge-gas with or without 1% hydrogen are discussed.