Browsing by Author "Temple, RB"

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    The extraction of beryllium by triisooctylamine in the presence of oxalate ion.
    (Australian Atomic Energy Commission, 1961-07) de Bruin, HJ; Temple, RB
    Beryllium ions can be extracted into organic solvents by tertiary amines, in the presence of compounds which give rise to anionic complexes. The nature of the extracted species has been investigated for the system beryllium/oxalate/triisooctylamine; it appears to be Be(C2O4)2 [Nh(i-C8H15)3]2. The beryllium/oxalate/water system has been examined by the method of pH titration in the absence of the organic phase. Under the conditions chosen, the dissociation constants for oxalic acid were found to be K1= 4.64 x 10-2 and k2 = 1.20 x 10-4, and the stability constants for the beryllium oxalate complexes β1=6.32 x 10³ and β2 =3.91 x 10 5.
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    The extraction of beryllium by triisooctylamine, the effect of the anionic complexing agent.
    (Australian Atomic Energy Commission, 1961-09) de Bruin, HJ; Kairaitis, D; Temple, RB
    The extraction of beryllium by triisooctylamine was measured over the pH range from 1 to 10, in the presence of malonic, maleic, succinic, phthalic, and salicylic acids. Values were obtained for the stability constants of the various metal-acid complexes by potentiometric titration. Values for these constants have not hitherto been published. The degree of extraction is dependent on the abundance of the anionic complex present in the aqueous phase and this is in turn dependent on the strength of the corresponding acid and the stability of the complex.
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    Formation constants of the beryllium thenoyltrifluoracetonates
    (Australian Atomic Energy Commission, 1961-09) de Bruin, HJ; Temple, RB
    The formation constants of the mono— and bis—thenoyltrifluoroacetone complexes of beryllium have been measured by a solvent extraction method. The values found are β1 = 3.40 x 105, and β2 = 1.21 x 1011, in a medium of ionic strength 0.1, at a temperature of 25º ± 0.1º.
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    The philosophy and practice of radioactive waste disposal
    (Melbourne University Press on behalf of The Australian Atomic Energy Commission, 1958-06-02) Temple, RB
    This general review is largely concerned with the problems of disposing of the large amounts of highly-radioactive waste that will result from a large-scale nuclear power program employing fission reactors. The dangers of dilution-dispersal are outlined, and particular attention is drawn to the possibility of biological reconcentration of the dispersed radioactivity. The conclusion is reached that it is imperative to find some method of permanently storing the activity in a non-leochable solid form, if the fullest use is to be made of nuclear power production. At present the "temporary expedient" of tank storage in liquid form is the only practicable method, but by I965 other methods will have to be found.
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    Reprocessing of homogeneous beryllium-based reactor fuel - a suggested scheme for the selective aqueous dissolution of the matrix
    (Australian Atomic Energy Commission, 1962-08) Farrell, MS; Temple, RB
    The matrix of a dilute homogeneous H.T.G.C, reactor fuel employing metallic beryllium as a moderator can be selectively dissolved by a caustic soda solution containing salicylate ion. At least 99 per cent, of the uranium and thorium can be recovered as insoluble solids, but in the case of irradiated material the uranium loss might be higher. Some decontamination of the resulting beryllium solution from fission products and Pa233 can also be obtained. A tentative chemical flowsheet is proposed on the basis of the results obtained.