Browsing by Author "Bull, PS"

Now showing 1 - 4 of 4
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    ANSTO's radioactive waste management policy: preliminary environmental review
    (Australian Nuclear Science and Technology Organisation, 1996-05) Levins, DM; Airey, PL; Breadner, B; Bull, PS; Camilleri, A; Dimitrovski, L; Gorman, T; Harries, JR; Innes, RW; Jarquin, E; Jay, G; Ridal, A; Smith, AM
    For over forty years radioactive wastes have been generated by ANSTO (and its predecessor the AAEC) from the operation of nuclear facilities the production of radioisotopes for medical and industrial use and from various research activities. The quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas especially those in countries with nuclear power program. Nevertheless in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO including spent fuel management treatment of effluents and environmental monitoring. It gives details of: relevant legislative regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken milestones and resource requirements.
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    Cation-exchange removal of copper from ammoniacal aqueous solution
    (Australian Atomic Energy Commission, 1973-03) Bull, PS; Evans, JV
    This report examines the nature of the adsorbed copper-ammine species in the resin phase, evaluates their stability constants and compares them with published data obtained in aqueous solution. It extends the study of the adsorption of copper by a strong acid-cation exchanger to solutions containing low concentrations of ammonia (0-0.032 M), and copper (10-lfM) and differentiates between the role of the ammonium ion and the free ammonia in the ion-exchange process.
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    The performance of powdered ion-exchange resins
    (Australian Atomic Energy Commission, 1973-03) Bull, PS; Evans, JV; Nicholson, FD
    The coating properties and ion exchange performance of powdered ion-exchange resins were examined in a small test facility. Satisfactory resin coatings were obtained with cation:anion resin ratios in the range 1:1 to 3:1 but use of a 9:1 resin ratio resulted in a high pressure drop across the coating. The 'settled resin volume proved to be a reliable guide to the coating performance of resin slurries. The ion-exchange capacity of the cation resin increased to a small extent with a decrease in sodium concentration in the influent water down to 500 μg ℓ-1. Within the ranges examined, resin ratio, resin loading and flow rate had no significant effect on cation capacity. The effect of exhaustion on the pressure drop characteristics and flocculating properties of various resin ratio's was investigated. The thermal stability of the powdered anion resin was markedly less than that quoted elsewhere for anion bead resin.
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    Spent HIFAR fuel elements behaviour under extended dry storage
    (Australian Nuclear Science and Technology Organisation, 1994-09) Ridal, A; Bull, PS
    Previously unpublished observations of the behaviour of HIFAR spent fuel under extended dry storage conditions are reported. The two fuel elements EC802 (Mark III type) were irradiated in 1966 first examined in hot cells in 1967 and again examined in hot cells in 1983 following 16 years of stage 11 years of which were in the ANSTO engineered dry storage facility. The elements showed negligible deterioration over this extended dry storage period lending considerable confidence to the viability of dry storage technologies for the long term storage of spent aluminium clad research reactor fuels.