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These values were obtained by recalculation of keff after removing each of the above sets of isotopes from each critical configuration. The worth of 135Xe was not included in the worth of the full set of fission products, since it is only present under HFP conditions. These results demonstrate that even in reactor critical configurations most of the fission-product worth is represented by the 25 burnup credit nuclides (listed in Table 2). 24 Table 10. 0064 )k Table 11. 0013 Reactor configuration Table 12.

63 5. 19 These experiments, used as the basis for cross-section validation studies, were selected as representative of $typical# low-enrichment UO2 LWR assemblies. 74 wt % 235U. Cadmium, boron, boral, boroflex, Ag-In-Cd, gadolinium, polyethylene, and stainless steel were used as absorbers in various experiments, and uranium, lead, and steel reflectors were included. 067. Both UO2 and mixed-oxide (MOX) fuels were used. Results are summarized in Figs. 5 and 6. Figure 5 shows the values of keff as a function of the AEG, based on the 27-group energy structure plotted with the results of experiment-based MOX calculations.

H. Wakeman and S. A. Ahmed, Evaluation of Burnup Credit for Dry Storage Casks, EPRINP-6494, Electric Power Research Institute, August 1989. 14. D. G. Napolitano and D. G. , March 1992. 15. O. W. Hermann and R. M. Westfall, $ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transmutation, Fission Product Buildup and Decay, and Associated Radiation Source Terms,# Sect. F7 of SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, NUREG/CR-0200, Rev.

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