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- W134266008 abstract "The release of radionuclides from spent fuel has been simulated for three different repository sites and waste package designs. Five distinct distributions for containment failure have been considered, and the release of nuclides from the UO/sub 2/ matrix, gap (including grain boundary), crud/surface layer, and cladding has been calculated with the AREST code. Separate scenarios involving incongruent and congruent release from the UO/sub 2/ matrix have also been examined. Releases for individual radionuclides have been evaluated relative to compliance with allowable NRC fractional release rates and EPA 10,000-year cumulative release limits. For the congruent matrix release scenario, spent fuel meets all EPA and NRC release criteria for all cases in which distributed containment failures are assumed. However, for the incongruent matrix release scenario, releases of several nuclides, notably Cs-135 and I-129, are found to be above their NRC limits. Additional studies, especially to determine whether release of nuclides from UO/sub 2/ is congruent or not, are needed before these general conclusions can be further substantiated." @default.
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- W134266008 date "1987-01-01" @default.
- W134266008 modified "2023-09-26" @default.
- W134266008 title "Analysis of spent fuel as a nuclear waste form" @default.
- W134266008 hasPublicationYear "1987" @default.
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