Cross Section Influence on Monte Carlo Based Burn Up Codes Applied to a GFR Like Configuration

Abstract

This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gascooled fast reactor (GFR)like configuration. Particularly, it shows a comparison between the two Monte Carlobased codes, each one adopting three different crosssection data sets, namely, JEFF3.1, JEFF3.1.2, and ENDF/BVII.1. Calculations have been carried out on the Allegro reactor, i.e.,آ an experimental GFRlike facility that could be built in the European Union as a GFR demonstration. Results include nuclear parameters, such as the effective multiplication factor and fluxes, as well as the atomic densities for some important nuclides versus burnup.