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Filtering by: Committee Member Wood, Terence M. Remove constraint Committee Member: Wood, Terence M. Decade 2020-2029 Remove constraint Decade: 2020-2029 Rights Statement In Copyright Remove constraint Rights Statement: In Copyright

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  • Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

    Creator:
    Yoshiura, Ramon K.
    Abstract:
    The development of nuclear fuel and materials requires is a continuous effort to investigate the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or other conceivable damage mechanics acquired during normal operation or accident scenarios throughout its lifetime. As in-core fuel property measurement techniques advance to support in...
    Resource Type:
    Dissertation

  • Fuel Dispersal Under LOCA Conditions

    Creator:
    Latimer, Griffen D.
    Abstract:
    Most operating power reactors use oxide fuel in the form of uranium oxide (UO2) which is robust against high temperatures but suffers from poor mechanical performance at high levels of burnup. Currently, the maximum average burnup in light water reactors in the US is 62.5 GWd/t, which is partially imposed...
    Resource Type:
    Dissertation
    Full Text:
    significant quantity of fragmented fuel particles were as fine as 5600μm, with some even surpassing the 2000