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Report No.
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Radiation attenuation in materials

Otani, Nobuo*; not registered; not registered

Neutron and neutron-induced gamma-ray flux attenuations have been estimated in various materials. Fluxes were obtained by one-dimensional transport code, ANISN-W(PNC), with nuclear group constants by RADHEAT-V3 system. Figures and tables representing attenuations in materials are given for fast, intermediate, thermal and total neutron fluxes, secondary gamma-ray flux, neutron does rate, and secondary gamma-ray does rate. Effects of selections of calculational conditions and/or nuclear group constants were also investigated for these radiation transport calculations. Data given in this report will be useful for the rough evaluation of shielding characteristics of structures in FBR plants.

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