A model of a ceramic breeding zone has been designed and manufactured for t
esting in the IVV-2M fission reactor. The model contains both lithium ortho
silicate and beryllium spheroid particles 1 to 2 mm in diameter. The struct
ural material is ferritic-martensitic stainless steel. In addition, a mocku
p of the model for verification of neutronics calculation methods has been
designed and manufactured. A special facility (Functional In-Reactor Invest
igations of Tritium-Breeding Models) has been designed, fabricated, and ass
embled at the reactor for studying the kinetics of tritium extraction from
the ceramic material under irradiation. Neutronic and thermohydraulic calcu
lations and an initial measurement of tritium release from the model under
reactor irradiation have been performed