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Breeder reactor fuels dissolution

The rate of dissolution of PUO2 in nitric acid is slower than UO2 and depends on the plutonium/uranium ratio, the methods used to fabricate fuel, and the conditions of irradiation. At one extreme, plutonium produced at low concentration in UO2 by transmutation dissolves almost as rapidly as the associated UO2. At the other extreme, plutonium present as PUO2 mixed mechanically with UO2 without proper sintering dissolves much more slowly and less completely than UO2. Plutonium present as a solid solution (U,Pu)02 at the concentration of 20 to 25 percent used in breeder-reactor fuel dissolves at an intermediate rate. ... [Pg.477]

The first-cycle raffinate wastes produced at the ICPP are the acid aluminum waste from various test reactor fuels, fluoride-bearing waste from zirconium-matrix fuel, a small amount of stainless steel sulfate waste from fuel from developmental reactors such as the Organic Moderated Reactor Experiment (OMRE), acid stainless steel nitrate waste from the electrolytic dissolution of Experimental Breeder Reactor-II (EBR-II) reactor fuel, and an acid waste from the recovery of uranium... [Pg.32]

See other pages where Breeder reactor fuels dissolution is mentioned: [Pg.94]    [Pg.7183]    [Pg.94]    [Pg.7183]    [Pg.927]    [Pg.927]    [Pg.7072]    [Pg.478]    [Pg.463]    [Pg.399]    [Pg.722]   
See also in sourсe #XX -- [ Pg.927 ]

See also in sourсe #XX -- [ Pg.927 ]

See also in sourсe #XX -- [ Pg.6 , Pg.927 ]



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