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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010087, respectively. I 2-24 March 31, 1997 (4:29pm) 3. CRITICALITY VALIDATION The design of spent fuel packages using burnup credit imposes unique requirements for criticality analysis method validation. Many components of the burnup credit criticality analysis method proposed in this topical report have been widely used in the design and licensing of conventional transportation and storage system packaging using the fresh fuel assumption. These methods must be shown to be valid for use in burnup credit applications.

2-17 The comtiosl factors for negative worth isotopes (neutron absorbers) are calculated in a similar but converse manner. 1%. 2-18 I I I I I I I I I I I I I I I I I I I I I I I I I The generic correction factor formula for isotopes which exhibit trends with respect to one or more of the four parameters (burnup, burnup*spectrum, burnup"initia1 enrichment, and burnup*specific power) Is also determined based on prediction interval. Therefore, the 95%confidence correction factor is: IEQ. 2-19 where: m = number of parameters (1,2,3, or 4) against which the specific isotope exhibited trends bj= slope for the trending parameter Hj = trending parameter (burnup, burnup*spectral index, burnup*initial enrichment, or burnup*specific power) n = number of data points Similar to the non-trended case, the sign between the bias and the total uncertainty depends on the type of isotope.

This approach ensures that the future calculated inventory for negative worth isotopes is not increased if the chemical assay indicated a higher measured value than the cofiesponding calculated value. Therefore, the correction factor for negative worth isotopes which exhibit trends with respect to one or more of the four parameters is: z=lq2SSR E=,Hji n-m fbuc =fneg = min [ l . 01 Eq. 3 describe methodology requirements for performing fuel depletion calculations and presented a statistical approach for calculating biases, uncertainties, and correction factors, based on calculated and measured isotopic values that can be used to bias future calculated isotopic values.

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