Abstract
Alpha-emitters on the surfaces of Zircaloy-4 cladding of PWR spent nuclear fuel have been examined at fuel burnup of 6900, 29,400 and 38,100 MWd/t. The amount of α-emitter on the inner and outer surfaces of cladding increased with fuel burnup, whereas the amount of plutonium on the outer surface remained roughly constant. The distribution of α-activity in the cladding varied with fuel burnup. The ratio of α-activity on the outer surface to total α-activity of the cladding decreased from about 50% at fuel burnup of 6900 MWd/t to 3% at fuel burnup of 38,100 MWd/t. The inventory of the α-activity in unit weight of cladding was found to be 4.75·102 and 4.35·104 Bq/g-cladding at fuel burnup of 6900 and 38,100 MWd/t, respectively. Adsorptive ability of the outersurface of irradiated cladding was about one order of magnitude greater than that of unirradiated Zircaloy-4 for α-emitters and some of the fission products except ruthenium.
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Sato, T., Hirabayashi, T., Sagawa, C. et al. Sorption behavior and inventory of alpha-emitters on the surfaces of spent nuclear fuel cladding. Journal of Radioanalytical and Nuclear Chemistry, Articles 163, 235–244 (1992). https://doi.org/10.1007/BF02034797
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DOI: https://doi.org/10.1007/BF02034797