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 resources for Actinide-Only Burnup Credit for PWR Spent Nuclear Fuel Packages

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I ~ I I I I I I I I . Eq. 2-11 As before, the trending test is applied to b,. The trending test formula for bz turns out to be similar to Equation 2-8 for testing b, except b, and Bi are replaced with b, and Bi*S,. Again, if the trending test indicates the value for the slope associated with burnup*spect:ral index is significant, the burnup*spectral index term is kept in the equation, and Eq. RUDraft 2-18 March 31, 1997 (4:29pm) x, = 1 + bl*B + b2*B*S + b3*B*E Eq. 2-12 As before, in order to determine b,, the sum of the squares of the residuals which is: (xi-1-b, *Bi-bz*Bi*Si-b3*Bi*EJ2 Eq.

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.

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. Validation of burnup credit criticality analysis methodologies requires consideration of a larger number of isotopes than is necessary with the fresh fuel assumption.

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