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Kotov, V.*; Savchuk, V.*; Zorin, B.*; Tazhibaeva, I.*; Kawamura, Hiroshi; Tsuchiya, Kunihiko; Druyts, F.*
Proceedings of 1st International Conference on Innovative Technologies; Reality and Prospect, p.91 - 98, 2011/00
no abstracts in English
Tsuchiya, Kunihiko; Longhurst, G.*; Chakin, V.*; Tazhibayeva, I.*; Druyts, F.*; Dorn, C. K.*; Kawamura, Hiroshi
JAEA-Conf 2008-011, p.55 - 58, 2009/01
no abstracts in English
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.
Tsuchiya, Kunihiko; Longhurst, G.*; Chakin, V.*; Tazhibayeva, I.*; Druyts, F.*; Dorn, C. K.*; Kawamura, Hiroshi
no journal, ,
Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. In fact, the nuclear properties of beryllium are its low atomic number, low atomic weight, low parasitic capture cross section for thermal neutrons, readiness to part with one of its own neutrons (n, 2n), and good neutron elastic scattering characteristics. Various problems of beryllium utilization are introduced for nuclear reactors and two points are proposed for the solution of irradiated beryllium wastes. Thus, it will be necessary to consider fundamental changes to the frame design, starting with the choice of beryllium material grade. Additionally, irradiation tests are planned for the design modification of beryllium materials. Beryllium material grades are selected for material modification and irradiation tests have been discussed. New measurement procedures in PIEs are also proposed for evaluation of lifetime extension. In this presentation, status and future plan of beryllium reflector development are introduced.
