Abstract
This work describes the influence of biological concrete shielding model on neutron flux in reactor pressure vessel simulator placed in VVER-1000 transport benchmark. It includes an analysis and a comparison of experimental and calculated values of neutron flux. The thermal neutron fluxes in RPV simulator were measured when the reactor vessel or biological shielding was cladded in a cadmium foil absorbing thermal neutrons. The calculations have been performed using both CENDL 3.1 and ENDF/B VII nuclear data libraries.
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