Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 39 / Number 1 / Pages 45-53
V. Kapychev, V. Gorokhov, D. Davydov, V. Demidov, Yu. Kazennov, V. Tebus, V. Frolov, A. Shikov, N. Shishkov, V. Kovalenko, A. Lopatkin, A. Marachev, V. Shishkin, Yu. Strebkov, L. Men'kin, A. Zyryanov
Fusion Science and Technology / Volume 39 / Number 1 / Pages 45-53
Format:electronic copy (download)
A model of a ceramic breeding zone has been designed and manufactured for testing in the IVV-2M fission reactor. The model contains both lithium orthosilicate and beryllium spheroid particles 1 to 2 mm in diameter. The structural material is ferritic-martensitic stainless steel. In addition, a mockup of the model for verification of neutronics calculation methods has been designed and manufactured. A special facility (Functional In-Reactor Investigations of Tritium-Breeding Models) has been designed, fabricated, and assembled at the reactor for studying the kinetics of tritium extraction from the ceramic material under irradiation. Neutronic and thermo-hydraulic calculations and an initial measurement of tritium release from the model under reactor irradiation have been performed.
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