Development of nuclear technologies is accompanied by the growth of radioactive waste including long-lived ones. The waste inside the Chernobyl 4-th unit is of particular importance because their amount is estimated as much as 20MCi. Under the circumstances a problem of operative characterization of the waste and their longterm disposal is urgent. The report presents an overview of the waste characterization method elaborated in NSC KIPT based on γ-activation analysis using bremsstrahlung of the high-current electron linac. On the other hand disposal of the radioactive waste faces a problem of confinement materials (including geological structures). Such materials have to keep their protection properties with respect to radionucliede transport under absorbed dose value up to ~10 7 Gy during thousand years or so. The elaborated methods for production of radionucliedetracers and operative determination of their diffusion coefficients into barriers under different doses of the braking photons are described.
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