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- W310306388 abstract "Results of measurements of thermal neutron density along the radii of rod fuel elements for a gas-cooled heavy water reactor are presented. The distributions obtained were used to calculate the screening factors and neutron density drops tn the walls of pipes and in air gaps between them. Results are compared with diffusion and kinetic equation results. The kinetic equation was solved for the neutron distribution in gray round cylinders. (W.D.M.)" @default.
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- W310306388 date "1959-10-31" @default.
- W310306388 modified "2023-09-27" @default.
- W310306388 title "DISTRIBUTION OF THERMAL-NEUTRON DENSITY ALONG THE RADII OF ROD FUEL ELEMENTS. EXPERIMENT AND COMPARISON WITH THEORY" @default.
- W310306388 hasPublicationYear "1959" @default.
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