Article ID Journal Published Year Pages File Type
1728752 Annals of Nuclear Energy 2013 6 Pages PDF
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.

► Measurement of 3He reaction rates in vicinity of RPV simulator of VVER-1000 Mock-Up. ► Calculations of 3He reaction rates in RPV vicinity using ENDF VII and CENDL 3.1. ► Cd ratios in vicinity of reactor pressure vessel simulator of VVER-1000 Mock-Up. ► Discrepancies between calculation and experiment.

Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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