STP1228

    Neutron Metrology in the Fuel Assemblies of a Material Test Reactor.

    Published: Jan 1994


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    Abstract

    Results are presented of detailed thermal and fast neutron measurements performed in all fuel and control assemblies of the HFR in Petten. The results give information about deviations of a general shape of vertical thermal and fast fluence rate distributions due to material transitions in the reactor core and different control assembly settings. Further it is demonstrated that the ratio of fast and thermal fluence rate at the various monitor positions in the assemblies give useful information for the (relative) local burn-up of the fuel.

    Keywords:

    thermal fluence rate, fast fluence rate, fuel assemblies, MTR, fuel burn-up, power production


    Author Information:

    Voorbraak, WP
    Netherlands Energy Research Foundation ECN, Petten,

    Paardekooper, A
    Netherlands Energy Research Foundation ECN, Petten,

    Polle, BN
    Netherlands Energy Research Foundation ECN, Petten,

    Freudenreich, WE
    Netherlands Energy Research Foundation ECN, Petten,


    Paper ID: STP15155S

    Committee/Subcommittee: E10.05

    DOI: 10.1520/STP15155S


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