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• W2227437542 abstract "Measurement and calculation of the axial power profile near the boundary of a moderated and non-moderated core is used to analyze the suitability of the neutron-physical process description, mainly the angular cross-section of a water-moderated uranium system. This is also an important issue because it affects the radiation situation above the partly flooded core of a water-moderated reactor. Axial power profiles of various fuel pins irradiated on reactor LR-0 were measured and the results were compared with MCNP6 code calculations using the ENDF/B-VII.0 nuclear data library. The calculated power profile in positions above the moderator level significantly underestimates experimental results. This might be caused by an improper description of the angular distribution of scattered neutrons in a water-moderated uranium system." @default.
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• W2227437542 date "2016-04-01" @default.
• W2227437542 modified "2023-09-25" @default.
• W2227437542 title "Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0" @default.
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• W2227437542 doi "https://doi.org/10.1016/j.anucene.2015.12.028" @default.
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