Burst Behaviour of Accident Tolerant Fuel Cladding Materials

  • Yousif Al Hosani

    Student thesis: Master's Thesis

    Abstract

    In March 2011, an accident occurred in Fukushima Daiichi Nuclear Power Plants by an earthquake and a hydrogen explosion occurred inside the reactor buildings. After the Fukushima nuclear accident, the nuclear industry was motivated and directed to research for possible methods to improve the safety of nuclear reactors. One of the proposed improvements was to adopt new fuel systems such that new designs will be more tolerant to accidents and as such, Accident Tolerant Fuel (ATF) concepts have been developed. In PWR and BWR reactors, Zr-based alloys is the most common material used in the fuel cladding. Currently in the United Arab Emirates, four reactors of APR1400 design have been constructed for the delivery of safe and clean energy. The APR1400 design utilizes a Zr-based alloy (Zirlo) as the fuel cladding for its reactor and will keep using them until a reliable and safe alternative is available. In this project, an evaluation model is developed to assess possible ATF candidates from a mechanical perspective and in specific tube burst behavior of the cladding will be the focus of the project. The burst behaviour will be evaluated during Large Break Loss of Coolant Accident (LBLOCA) as it provides severe conditions to the cladding and tube burst behaviour is a concern. MAAP5 code will be used to evaluate the environmental conditions that the cladding experience during a LOCA event and use it to perform burst analysis on the different claddings. The focus of this research will be to evaluate the response time (burst time) of the cladding to the burst behavior and compare the results to the conventional fuel system used in the current nuclear reactors.
    Date of AwardMay 2022
    Original languageAmerican English

    Keywords

    • Accident Tolerant Fuel
    • LOCA
    • Burst
    • Cladding
    • FeCrAl
    • Zircaloy-4
    • MSc Thesis
    • MSc in Nuclear Engineering.

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