Download Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel by United States. Dept. of Energy. Yucca Mountain Project PDF

By United States. Dept. of Energy. Yucca Mountain Project Office.; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information

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Extra info for Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

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In any depletion code an approximation of the energy distribution of the flux must be made. In a point depletion code, such as SAS2H, the geometric data that can be handled is limited so a general algorithm is set up and validated. The algorithm selected for assembly models performed for this study is: 1) Divide the assembly cross sectional area by the number of removable burnable absorber rods (or by the number of guide tubes plus one for the instrumentation tube if there are no burnable absorbers).

1 UO, Fuel Critical Experiments The 19 UO, critical experiments from 8 references are selected to examine 6 different aspects of spent nuclear fuel package criticality: Neutron interaction between PWR type fuel assemblies Effectiveness of neutron flux traps between fuel assemblies Effect of voiding on the effectiveness of flux traps DRAFT 3-2 March 30, I997 (10:45pm) @ Effectiveness of neutron absorber plates and rods to reduce interaction between fuel assemblies @ Reactivity effect of commonly used package shielding materials @ Neutron spectra shift or relative neutron moderation caused by dissolved boron.

The validation methodology consists of best-estimate analysis for determining isotopic concentrations computationally, and the statistical approach in determining biases, uncertainties, and correction factors. 2 computer code package. Using this specific code, data, and methodology, a set of isotopic correction factors was developed that can be used directly in modifying future calculated inventory of the selected actinides. Therefore, this section requests acceptance of the chemical assay data for the selected actinides as summarized in Table 2-1, the method for calculating isotopic c o m t i o n factors for the selected actinides, and the use of SAS2H/27BURNUPLlB as a computational tool in calculating the quantity of the selected actinides in spent fuel assemblies.

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