This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gas-cooled fast reactor (GFR)-like configuration. Particularly, it shows a comparison between the two Monte Carlo-based codes, each one adopting three different cross-section data sets, namely, JEFF-3.1, JEFF-3.1.2, and ENDF/B-VII.1. Calculations have been carried out on the Allegro reactor, i.e., an experimental GFR-like 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 burn-up.
Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
Manuscript received July 24, 2014; final manuscript received January 4, 2015; published online May 20, 2015. Assoc. Editor: Jay F. Kunze.
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Chersola, D., Lomonaco, G., and Mazzini, G. (May 20, 2015). "Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration." ASME. ASME J of Nuclear Rad Sci. July 2015; 1(3): 031004. https://doi.org/10.1115/1.4029521
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