Browsing by Author "Costello, JM"

Now showing 1 - 6 of 6
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    An assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastes
    (Australian Atomic Energy Commission, 1982-10) Costello, JM; Wilson, EG
    The principles of management and disposal of highly radioactive wastes contained in spent fuel from nuclear power generation are described. The status of developments in spent fuel reprocessing high-level waste solidificaton and geologic isolation is reviewed. Some generic studies on the possible range of annual radiological doses to individuals from waste repositories are discussed and compared with doses from some existing nuclear power and fuel cycle operations and with the dose received annually from an average background of naturally occurring radiation.
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    High-level radioactive waste disposal : the international scene
    (Australian Atomic Energy Commission, 1983-11-30) Costello, JM
    The status of developments in spent fuel reprocessing, high-level wast solidification and geologic isolation is reviewed. Some generic studies on the possible range of annual radiological doses to individuals from waste repositories are discussed and compared with doses from existing nuclear power and fuel cycle operations, and with the dose received annually from the naturally occurring radiation background. The significance of neptunium-237 in dose estimation is discussed, together with technological trends in separation and disposal of long lived actinide elements.
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    Papers presented to the AAEC symposium on uranium processing, Lucas Heights, 20-21 July, 1972
    (Australian Atomic Energy Commission, 1972-09) Miles, GL; Harltey, FR; Butler, RD; Henley, KJ; Cooper, RS; Kelly, A; Goldney, LH; Canning, RG; Gooden, JEA; Baillie, MG; Thomas, JA; Hardy, CJ; Alfredson, PG; Costello, JM; Silver, JM; Richmond, M
    Review of nuclear fuel cycles and world trends; Conventional processes to produce yellow cake; Carbonate leaching of uranium ores, a review; The application of mineralogy to uranium ore processing; Extraction investigations with some Australian uranium ores; Planned changes in the Mary Kathleen treatment plant for future operations; Possible trends and methods for the production of high purity products; Review of methods and technology for the reproduction of high purity products; Review of methods and technology for the production of uranium hexafluoride; Capital and production costs for the production of uranium hexafluoride; The market for Australian conversion services.
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    Radioactive waste management
    (Australian Atomic Energy Commission, 1977-04) Costello, JM
    How are radioactive wastes produced in nuclear power generation? What are the quantities involved? What procedures are available for their storage, treatment and disposal? These and other questions concerning radioactive waste management are discussed.
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    Reduction of capital costs in reprocessing power reactor fuels: a design study
    (Australian Atomic Energy Commission, 1973-09) Costello, JM; Levins, DM
    The design and cost structures of conventional types of commercial reprocessing plant have been reviewed. Process functions offering the greater potential saving in capital cost have been identified. Unorthodox approaches to philosophies of plant layout, maintenance procedures, and radiation shielding have been formulated with the primary aim of reducing capital cost. Four conceptual designs have been made of a large scale reprocessing plant based on existing shear leach-solvent extraction technology, incorporating novel equipment types and unorthodox design philosophy. Preliminary capital cost estimates for the designs are in the range $37-41 x 10 6, indicating a 30-37% reduction in comparison with a conventional plant of identical capacity and scope. Additional costs exceeding $30 x 10 6 could be incurred for refinement to effluent treatment and storage systems envisaged for environmental protection for any type of reprocessing plant.
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    Wastes and waste management in the uranium fuel cycle for light water reactors
    (Australian Atomic Energy Commission, 1975-08) Costello, JM
    The manufacturing processes in the uranium fuel cycle for light water reactors have been described with particular reference to the chemical and radiological wastes produced and the waste management procedures employed. The problems and possible solutions of ultimate disposal of high activity fission products and transuranium elements from reprocessing of irradiated fuel have been reviewed. Quantities of wastes arising in each stage of the fuel cycle have been summarised. Wastes arising from reactor operation have been described briefly.