Browsing by Author "Hesse, EW"

Now showing 1 - 4 of 4
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    A data transmission system for the centrifuge enrichment plant safeguards project.
    (Australian Atomic Energy Commission, 1987-04) Hesse, EW
    A novel data transmission system was developed to enable the Australian Safeguards Office (ASO) in Sydney to monitor remotely the running of an experimental enrichment facility at the Lucas Heights Reserch Laboratories using Telecom telephone lines. The system allowed ASO to monitor the enrichment flows and activity in sensitive areas of the plant by means of a master computer at ASO and a slave computer at Lucas Heights. The slave computer sent requested data and scanned video pictures to determine intrusive changes to the plant. Detailed descriptions of the transmission system and method of operation are given together with an outline of experience obtained during a three-month surveillance of the facility.
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    EQUICORE II: a two dimensional coupled hydraulic-neutronics code for calculating the equilibrium and time dependent burnup states of pressure tube type reactors.
    (Australian Atomic Energy Commission, 1973-08) Hesse, EW
    The Equicore II code calculates the burnup, power distribution and coolant conditions of pressure tube type reactors for both the equilibrium and time dependent core conditions. The code has been designed to be both easy to use and economic in computing time. To achieve this, the overall core burnup and hydraulic performance is obtained by considering only a few representative fuel assemblies and by using flux distributions derived from an RZ-diffusion calculation, based on volume elements containing the average properties of these representative fuel assemblies. A separate RZ supercell calculation model is available to determine the detailed flux and power variation between selected fuel assemblies and the average properties within radial zones of the core. The code also incorporates a user-oriented facility which allows, at any stage of the burnup calculation, the determination of such things as space dependent temperature coefficients and time dependent variation of xenon concentration. This report describes the models used in the code and gives the data requirements.
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    Equilibrium model for calculation of burnup in a recirculating pebble bed reactor.
    (Australian Atomic Energy Commission, 1966-09) Bicevskis, A; Hesse, EW
    The general problem of burnup calculations for a pebble bed reactor is discussed An efficient calculational scheme is developed by treating operation at equilibrium with a random distribution of pebbles. Assuming a constant flux level and spectrum, analytical solutions are obtained for time averaged nuclide concentrations. With a specified feed composition average power density, and burnup consistent values of average nuclide concentrations and flux spectrum are derived in an iterative manner, It is shown by physical reasoning and numerical calculation that the assumptions are justified for the large pebble bed reactors based on PuO2 — ThO2 — BeO fuels selected for a reactor feasibility study. The spectrum weighted improved one—group treatment lends itself to efficient coupling of burnup and power plant optimization studies and it may also find application to other reactor systems.
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    The space dependent treatment of pebble bed reactor fuel management using the burnup code FRIZLE
    (Australian Atomic Energy Commission, 1967-03) Hesse, EW
    An outline is given of the model used in the FRIZLE code complex in order to treat the two dimensional space dependent fuel management problem. The model is an extension of the zero dimensional burnup model, which allows the linking up of some existing codes. The code complex is capable of determining, for all envisaged pebble bed reactor fuel management schemes, the core power distribution based on the calculated average composition and temperature in specified core zones. The code is used for assessing several practicable management schemes applicable to a pebble bed reactor. These show that the same achievable burnup is obtained as with the zero dimensional method, based on the assumption of infinite recirculation. However, because of the markedly different core power distributions produced by various schemes, it is more important to arrange the management to reduce the core size and capital cost, than to increase burnup. Details are given of the code complex and data requirements.