Browsing by Author "Anderson, PJ"

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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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    Low enrichment Mo-99 target development program at ANSTO
    (Argonne National Laboratory, 2002-11) Donlevy, TM; Anderson, PJ; Storr, GJ; Yeoh, G; Beattie, D; Deura, M; Wassink, D; Braddock, B; Chant, W
    The Australian Nuclear Science and Technology Organisation (ANSTO, formerly AAEC) has been producing fission product Mo-99 in HIFAR, from the irradiation of LEU UO2 targets, for nearly thirty years. Over this period, the U-235 enrichment has been increased in stages, from natural to 1.8% then finally to 2.2%. The decision to provide Australia with a replacement research reactor (RRR) for HIFAR has created an ideal opportunity to review and improve the current Mo-99 production process, right from target design through to chemical processing and waste management. The major focus at this point in time is the development of a LEU target, initially suitable for irradiation in HIFAR and, with subsequent modification, suitable for irradiation in the RRR. We have entered into collaboration with Argonne National Laboratory (RERTR) to develop such a target using uranium metal foil with U-235 enrichment of less than 20%. The first trial irradiation of this target is planned in December 2000 and it will be processed using the current Mo-99 production process at ANSTO. The review of this trial will determine the program for further irradiations.