[en] Requirements for shielding materials for spent nuclear fuels transportation, are formulated. Calculated and experimental investigations of radiation attenuation at different shielding compositions are carried out. It is shown that composition of steel and borated titanium hydride is the most efficient with respect to total attenuation of γ radiation and neutron flux. This composition is the most efficient for transportation of fuels with high burnup in gaseous coolant

[en] Basic requirements to ensure nuclear safety in developing shipping casks for transporting spent nuclear fuel are reported. A classification of mechanical damages of the casks and their consequences is put forward. It is based on the current ''Rules of nuclear safety in transport of spent nuclear fu (PBYa-06-08-77). The requirements proposed were used in developing the TK-6 and TK-10 casks. It is concluded, that in terms of nuclear safety the TK-6 and TK-10 casks are safe even at substantial damages resulting in movement of tens (in case of fuel release from fuel elements) or hundreds (no fuel release) kilograms of the spent fuel

[en] Shielding properties of two mockups of shields for transport containers for spent fuels are investigated. Compositions, containing the layers of: St. 3 steel 35 cm thick, titanium hydride with boron-15 cm, St. 3-20 cm, titanium hydride with boron-15 cm, St. 3-15 cm are considered. Neutron spectra are measured, using a set of the threshold and resonance detectors and scintillation spectrometer with stilbene crystal and ³He-spectrometer as well. Spatial distributions neutron and gamma radiation flux densities are calculated by the DOT-111 and ATIKA programs. The data obtained shows, that essential deformations of neutron spectrum occur when moving from steel layer to the layer of titanium hydride with boron. Spectrum softening in energy range > 3 MeV occurs behind the steel screens, while its hardening occurs behind the layer of titanium hydride with boron. Conclusion is made about advisability of application of titanium hydride-base composition as shields for transport containers

[en] The paper considers the main principles involved in the organization in the USSR of the transport of irradiated nuclear power plant fuel by special trains, with account taken of experience already gained. Certain provisions of the current USSR regulations for safety and physical protection in the transport of nuclear materials are discussed. (author)

[en] The paper deals with the results of investigation of gamma-neutron radiation formation behind the radiation shielding of a shipping cask with WWER-1000 spent fuel. The cask short description is given. The radiation shielding structure, spent fuel characteristics, devices used are described. The way of neutron spectra reproduction and the estimate of different energy neutron dose commitment are presented which have been used to find the correction factors for standard radiometer indications