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Browsing Scientific and Technical Reports by Subject "Actinides"

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    Development of solvent extraction processes for the H.T.G.C.R. fuel cycle, Part 1 - design of a flow-sheet for the recovery of actinides.
    (Australian Atomic Energy Commission, 1965-06) Baillie, MG; Ryan, RK
    A preliminary flowsheet for the recovery and decontamination of residual actinides in spent H.T.G.C.R. fuel has been designed. A calculation method for the multicomponent liquid—liquid extraction system H20 - UO2(NO3)2 - Th(NO3)4 - Be(N03)2 - HNO3 - TPP - Kerosene using the limited equilibrium data available is described. The flowsheet which has been designed incorporates a novel "split contactor" concept which is necessary to prevent third phase problems.
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    Development of solvent extraction processes for the H.T.G.C.R. fuel cycle, Part 3 - chemical data for the extraction of actinides and fission products from aqueous beryllium sulphate solutions using amines.
    (Australian Atomic Energy Commission, 1968-01) Fardy, JJ; Farrell, MS
    Chemical data are presented for the actinides (uranium, plutonium and thorium), the fission products (cerium, zirconium, niobium and ruthenium) and beryllium in the extraction of these from beryllium sulphate solutions by amines, in particular Primene-JMT and Alamine-336. The data so obtained define the major chemical parameters requiring control in a solvent extraction process to decontaminate beryllium sulphate, and indicate that the use of the solvent Primene-JMT/Solvesso-100 will adequately remove the uranium, thorium, plutonium, cerium, zirconium and niobium without extracting significant quantities of beryllium. Ruthenium is not highly extractable and strontium and caesium are extractable only in trace quantity. Although this process will be adequate for primary decontamination of the beryllium sulphate, a further step to remove residual ruthenium, strontium and caesium may be required. The actinides with the extracted fission products are readily stripped from the amine phase with nitric acid, thus permitting recovery of the actinides by a conventional tributyl phosphate process. The amine phase is readily converted back to the free-base form using sodium carbonate. This is necessary to prevent recycling of the nitrate which would inhibit the extraction of thorium, plutonium and the fission products.
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    The environmental behaviour of uranium
    (International Atomic Energy Agency, 2023) Carvalho, FP; Fesenko, S; Harbottle, AR; Lavrova, T; Mitchell, NG; Payne, TE; Rigol, A; Thorne, MC; Ulanowski, A; Vidal, M; Voitsekhovych, O; West, JM; Yankovich, TL
    This publication is one of the series of IAEA publications on the environmental behaviour of naturally occurring radionuclides It outlines uranium behaviour in different environments, as well as its transfer to, and metabolism in, humans The publication also provides concepts, models and data required for the assessment of the impacts of uranium on non-human biota Assessing the environmental and health effects of uranium poses specific challenges because of the combination of different types of hazard and potential exposures Therefore, both the radiotoxicity and chemical toxicity of uranium are considered in this publication.