Transient Convective Delayed Neutron Precursors of 235U for the Molten Salt Reactor Experiment

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    Abstract

    This work investigates the delayed neutron precursors from the fission of 235U in molten salt reactors. The six delayed neutron groups predict the spatial distribution by the advective transport for radioactive mass transfer in the Molten-Salt Reactor Experiment (MSRE). Mole, using the framework of the Multiphysics Object-Oriented Simulation Environment (MOOSE), was used to compute the delayed neutron concentration of the whole system. This approach can be used for analysis of reactivity in circulating conditions. The effect of delayed neutron concentrations on the static or dynamic behavior of the system in MSRE was analyzed. Using this approach, the pattern and validation of delayed neutron for a range of parameters of interest are reported and discussed herein.

    Original languageEnglish
    Title of host publicationProceedings of the International Conference on Physics of Reactors, PHYSOR 2022
    PublisherAmerican Nuclear Society
    Pages1328-1337
    Number of pages10
    ISBN (Electronic)9780894487873
    DOIs
    StatePublished - 2022
    Event2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States
    Duration: May 15 2022May 20 2022

    Publication series

    NameProceedings of the International Conference on Physics of Reactors, PHYSOR 2022

    Conference

    Conference2022 International Conference on Physics of Reactors, PHYSOR 2022
    Country/TerritoryUnited States
    CityPittsburgh
    Period05/15/2205/20/22

    Funding

    This work has been carried out in the framework of the NEAMS (Nuclear Energy Advanced Modeling and Simulation) program supported by the United States Department of Energy.

    Keywords

    • MSRE
    • convection
    • delayed neutrons precursors
    • uranium-235

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