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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Additional resources for Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages
Column 1 of Table 3-2 summarizes key criticality analysis parameters. The range of conditions that can be anticipated for spent fuel packages is provided in column 2 of the table. , UO, and MOX) from several experimental sources have been selected for burnup credit criticality analysis method validation. Column 3 of Table 3-2 provides the range of spent fuel composition and physical system characteristics that are covered by the critical experiments selected. The experiments cover a wide range of fuel compositions and anticipated spent fuel package physical conditions.
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).
700-in. 870-in. 870-in. 990-in. 990-in. pitch. 767 ppmb Ref. 3-11 Ref. 3-11 Ref. 3- 11 Ref. 3- 1I Ref. 3- 11 Ref. 52-in. 56-in. 5641. 735-in. 792-in. pitch Ref. 3-12 Ref. 3-12 Ref. 3- 12 Ref. 3- 12 Ref. 3-12 Ref. 386-in lattice spacing Ref. 3-14 Ref. 3-14 Ref. 3-14 Ref. 3- 14 Ref. 3-14 Ref. 32-in lattice spacing Ref. 3-14 Ref. 3-14 Ref. 3-14 Ref. 0009 March 30,1997 (257pm) I I I I I I I I I I I I I I I I Table 3-1. Critical Benchmark Experiments for Burnup Credit Method Validation with CSAS/27BURNUPLIB Calculated Results (Continued) I Experiment Case Enrichment U-235 Description Original Reference' (Wt %) I I I I I I I I I I I PUP I PUP I I I I I I UOJFQO, triangular I I I I I Lattice NaterFuel Volume ALA' kat std.
Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages 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