STP1001

    Analysis of Neutron Emission on PWR Spent Fuel Assemblies for Burn-Up Assessment

    Published: Jan 1989


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    Abstract

    A series of passive neutron measurements performed on TIHANGE I spent fuel assemblies were analyzed for comparison with calculated burn-up values and neutron emission rates. The burn-up range of these assemblies was between 10 and 45 MWd/kg and the cooling time varied from 1 to 8 years approximately.

    The measurements, performed with 235U fission chambers, were correlated with neutron emission and burn-up by means of the ORIGEN-2 point model depletion code, taking into account the irradiation history. A fairly good correlation was found between the 244Cm contributions, as deduced from the measurements corrected with ORIGEN-2, and the burn-up values as calculated with fuel management codes. It was noticed that the ratio of the calculated (ORIGEN-2) neutron emission and the measured neutron detection varied with the burn-up.

    Keywords:

    PWR spent fuel, neutron emission rate, burn-up measurement


    Author Information:

    Debrue, J
    SCK/CEN, Mol,

    Raedt, CD
    SCK/CEN, Mol,

    Minsart, G
    SCK/CEN, Mol,


    Paper ID: STP10132S

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP10132S


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