Browsing by Author "Barnes, RK"

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    An analysis of molybdenum-99 expiry times in sodium pertechnetate derived from a dry-bed generator
    (Australian Nuclear Science and Technology Organisation, 2000-03) Barnes, RK; Anderson, PJ; Stimson, D; Chapman, J; Druce, MJ
    Fission-based 99 Mo/ 99m Tc generators have undergone evolutionary changes since they were first manufactured at the Lucas Heights Laboratories in the late 1960s for the Australian nuclear medicine community. This study is aimed at understanding the chemistries which influence the behaviour of the heterogeneous molybdenum-alumina system in a chromatographic generator. The quality of sodium pertechnetate derived from a dry-bed generator is enhanced when compared with the traditional wet-bed technologies. Data is presented which compare the extent of 99Mo desorption from both wet and dry-bed chromatographic generators. The expiration times for sodium pertechnetate based on 99Mo breakthrough are significantly greater for the recently developed dry-bed generators.
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    Development of a pilot plant for the removal of rhenium from molybdenum trioxide
    (Australian Atomic Energy Commission, 1985-12) Lee, EJ; Sorby, PJ; Barnes, RK; Boyd, RE
    Reagent grade molybdenum trioxide used as a target material for the preparation of Tc-99m pharmaceuticals contains trace amounts of rhenium. A simple charcoal adsorptions process has been developed to remove rhenium selectively from molybdenum before neutron irradiation. Details are given of the design and operation of a pilot plant in which 17 kg of molybdenum trioxide was produced having a rhenium content of less than 1 x 10 -6 mu g g -1. Although contamination of the Tc-99m by inactive rhenium and 188 Re was effectively eliminated 188 Re resulting from the irradiation of tungsten impurity in the molybdenum trioxide target was still present.
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    SPECACT, a fortran program for the routine calculation of the specific activity of fission-produced Molybdenum-99
    (Australian Atomic Energy Commission, 1986-01) Barnes, RK; Hetherington, ELR
    The specific activity of 99 Mo is an important factor in the production of 99 Mo/Tc-99m generators used in nuclear medicine. Molybdenum-99 formed via the fission route is not carrier free but is contaminated by a number of stable molybdenum isotopes formed concurrently during neutron irradiation of the uranium target. The specific activity of fission-based 99 Mo is therefore a function of irradiation time and post-irradiation decay. A computer program written in FORTRAN is presented for defining routinely the specific activity of fission-based 99 Mo.