comparative study on neutron data in integral experiments of myrrha mockup critical cores in the venus-f reactor

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ID: 239377
2017
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Abstract
VENUS-F is a fast, zero-power reactor with 30% wt. metallic uranium fuel and solid lead as coolant simulator. It serves as a mockup of the MYRRHA reactor core. This paper describes integral experiments performed in two critical VENUS-F core configurations (with and without graphite reflector). Discrepancies between experiments and Monte Carlo calculations (MCNP5) of keff, fission rate spatial distribution and reactivity effects (lead void and fuel Doppler) depending on a nuclear data library used (JENDL-4.0, ENDF-B-VII.1, JEFF-3.1.2, 3.2, 3.3T2) are presented.
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antonn2017epjcomparative Use this key to autocite in the manuscript while using SciMatic Manuscript Manager or Thesis Manager
Authors ;Krása Antonín;Kochetkov Anatoly;Baeten Peter;Vittiglio Guido;Wagemans Jan;Bécares Vicente
Journal utilitas mathematica
Year 2017
DOI
10.1051/epjconf/201714606019
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