"Ko\u0161\u0165\u00E1l, M." . . . "RIV/68407700:21340/13:00200384" . . "000315550500017" . "The effect of biological shielding on neutron transport in the VVER-1000 mock-up on the LR-0 research reactor"@en . . "53" . "21340" . "Ju\u0159\u00ED\u010Dek, V." . . . . "6"^^ . . "The effect of biological shielding on neutron transport in the VVER-1000 mock-up on the LR-0 research reactor" . "6"^^ . . "Rypar, V." . . . . . "Nov\u00E1k, E." . . "10.1016/j.anucene.2012.09.018" . . . "2"^^ . . "RIV/68407700:21340/13:00200384!RIV15-MSM-21340___" . "Mil\u010D\u00E1k, J\u00E1n" . "Kolros, Anton\u00EDn" . "71380" . "Annals of Nuclear Energy" . . "The effect of biological shielding on neutron transport in the VVER-1000 mock-up on the LR-0 research reactor"@en . . "P(ED2.1.00/03.0108), Z(MSM2672244501), Z(MSM6840770040)" . "[C231749201F0]" . . "The effect of biological shielding on neutron transport in the VVER-1000 mock-up on the LR-0 research reactor" . "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."@en . . "Thermal neutron flux; VVER-1000, LR-0; ENDF/B VII; CENDL 3.1; MCNP"@en . "3" . . "GB - Spojen\u00E9 kr\u00E1lovstv\u00ED Velk\u00E9 Brit\u00E1nie a Severn\u00EDho Irska" . "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." . "0306-4549" .