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Isotopic Analysis of Natural UO2Fuel Irradiated to 22000 MWd/MTU. Theory vs Experiment

Joseph C. Stachew

Open publisher page 3 citations

Abstract

The uranium and plutonium isotopic distributions of 45 irradiated fuel rods of natural uranium dioxide are compared to theoretical predictions made using three-dimensional P-1 neutron diffusion techniques. The calculations are different in that normalization to experimental results is made only by use of the total core energy output and measured critical rod-bank heights. This is in contrast to normalizing each individual fuel-rod burnup to the experimental value and then investigating resultant isotopic distributions in the rod. The comparison indicates good agreement but identifies the need for a spatial spectrum variation of the 238U epithermal resonance absorption cross section and improved time -dependence of the 238U and 239Pu cross sections.

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What this paper is about

The uranium and plutonium isotopic distributions of 45 irradiated fuel rods of natural uranium dioxide are compared to theoretical predictions made using three-dimensional P-1 neutron diffusion techniques. The calculations are different in that normalization to experimental results is made only by use of the total core energy output and measured critical rod-bank heights. This is in contrast to normalizing each individual fuel-rod burnup to the experimental value and then investigating resultant isotopic distributions in the rod. The comparison indicates good agreement but identifies the need for a spatial spectrum variation of the 238U epithermal resonance absorption cross section and improved time -dependence of the 238U and 239Pu cross sections.

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Available abstract

The uranium and plutonium isotopic distributions of 45 irradiated fuel rods of natural uranium dioxide are compared to theoretical predictions made using three-dimensional P-1 neutron diffusion techniques. The calculations are different in that normalization to experimental results is made only by use of the total core energy output and measured critical rod-bank heights. This is in contrast to normalizing each individual fuel-rod burnup to the experimental value and then investigating resultant isotopic distributions in the rod. The comparison indicates good agreement but identifies the need for a spatial spectrum variation of the 238U epithermal resonance absorption cross section and improved time -dependence of the 238U and 239Pu cross sections.

Key concepts: Uranium dioxide, Burnup, Natural uranium, Plutonium-239, Neutron capture, Uranium, Rod, Enriched uranium

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