Spectral studies of 252Cf neutron emission in three-sectional labyrinth

Data of model experiment carried out for test of calculating methods applied in designing communication-transport labyrinths in solid biological shielding of nuclear facilities are presented. Neutron spectra in the model labyrinth were measured. 252Cf neutron source with fission spectrum and the same source in the polyethylene moderator were placed at the inlet of the labyrinth. Analysis of fluence production ad equivalent dose along the geometrical axis of the labyrinth is conducted on the basis of the obtained spectra. Simulation of conditions permitting to practically reduce the radiation dose in the labyrinth (design of blind alley, utilization of facing materials, production of diaphragms and barriers) is carried out