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- W188286145 abstract "Recycling of plutonium in light water reactors in the Federal Republic of Germany began in 1966, and through the subsequent years, has reached a commercial state. Irradiation programs and post irradiation examinations (PIEs) of modern, highly soluble mixed oxide (MOX) fuel of the ammonium uranyl plutonyl carbonate/optimized co-milling type have been carried out since 1981 to evaluate fuel performance and to verify the data base for design. The results of PIEs on MOX fuel rods with burnups ranging from 6 to 47 GWd/ton heavy metal are described. The dimensional behavior of the MOX fuel rods is found to be almost identical to that of UO[sub 2] fuel rods. Densification and swelling of MOX fuel are governed by the behavior of the UO[sub 2] matrix as well as the porosity that develops in the MOX agglomerates. A comparison of the relevant physical properties of UO[sub 2] and MOX fuel shows that no distinct difference in the fission product release behavior of defective MOX fuel is to be expected." @default.
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- W188286145 date "1993-04-01" @default.
- W188286145 modified "2023-09-27" @default.
- W188286145 title "Irradiation behavior of UO[sub 2]/PuO[sub 2] fuel in light water reactors" @default.
- W188286145 hasPublicationYear "1993" @default.
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