Browsing by Author "Donlevy, TM"
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- ItemLow 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, WThe 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.
- ItemThe return of Australia's intermediate level waste from France(Australiasian Radiation Protection Society, 2012-10-16) Dimitrovski, L; Donlevy, TMOn 1 May 2012, the Australian Nuclear Science and Technology Organisation announced that it will apply for a licence to construct an interim storage facility for Australian radioactive waste generated by several decades of nuclear medicine production and scientific research. Plans for the proposed interim storage facility will be assessed by the independent regulator, the Australian Radiation Protection and Nuclear safety Agency, ARPANSA, which will conduct a public consultation process. The proposed new storage facility at Lucas Heights (subject to regulatory approval) would enable Australia to meet obligations to repatriate Australian waste currently being reprocessed in France and due, under arrangements established by Governments in the 1990s, to return to Australia by the end of 2015. It is anticipated that this proposed interim facility would operate at Lucas Heights for up to five years from late 2015 - while planning is underway for the siting, design and construction of a national radioactive waste management facility anticipated to be operational by 2020. This talk will summarise the history of ANSTO's spent fuel management and past shipments to the USA, UK and France, focus on the intermediate level waste arising from reprocessing in France and the specially designed package it will be transported and stored in; and, expand on the plans underway at ANSTO to enable it to receive and manage this waste by the agreed deadline in 2015.
- ItemSynthesis of a new cage ligand, SarAr, and its complexation with selected transition metal ions for potential use in radioimaging(Royal Society of Chemistry, 2001-07-12) Di Bartolo, NM; Sargeson, AM; Donlevy, TM; Smith, SVA new hexaazamacrobicyclic cage ligand, 1-N-(4-aminobenzyl)-3,6,10,13,16,19-hexaazabicyclo[6.6.6]eicosane-1,8-diamine (SarAr) has been designed for conjugation to proteins. SarAr was synthesised and characterised by microanalyses, 1H NMR and electrospray mass spectrometry. The complexation of selected transition metal ions (Cu(II), Ni(II) and Co(II) at 10−6 M) by SarAr was complete within 30 min over pH 6 to 8. The [64Cu(SarAr)]2+ complex was investigated with a view to applications in radioimaging. The [64Cu(sar)]2+ complex was found to be stable in human plasma for at least 174 h and biodistribution studies in mice, showed that the [64Cu(SarAr)]2+complex was rapidly excreted through the renal system unlike the free 64Cu2+. Overall, the simple synthesis, ready complexation behaviour of SarAr, the kinetic inertness of the [Cu(SarAr)]2+ complex to dissociation of 64Cu and its facile elimination from mice make it an attractive prospect for use in nuclear medicine. © The Royal Society of Chemistry 2001