Research and development of recycling technology of irradiated beryllium

Kotov, V.*; Savchyk, V.*; Zorin, B.*; Tazhibayeva, I.*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Druyts, F.*

no journal, , 

Processing of irradiated beryllium allows to improve economical and ecological characteristics of its further utilization. Main goals of purification are to decontaminate beryllium from radioactive products, including long-lived H and Co, and to restore the mechanical properties of beryllium. At present there are no technologies for industrial processing of irradiated beryllium. The paper discuss on the technology and its modifications, which are based on transfer of metal beryllium into chloride and its purification from tritium and cobalt. The laboratory research of this approach showed positive results but limitations as for productivity and total consumption of the reagents. Productivity has sufficient impacts on balance of the heat effects of chemical reaction, requirements for dispersion of initial product, as well as it changes efficiency of the chemical processes and phase composition ratio of the reagents in some parts of technological facility. We considered the possibilities to provide required temperature modes for the sections, where beryllium is transferred into chloride and its reverse conversion, and to define purity degree by measuring the non-radioactive isotopes of hydrogen and cobalt. Potentials of the alternative technologies were considered as well.