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    Transport Calculation of the Gamma Field in the Ex-Core Region of the KrŠko Pressure Water Reactor

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    Results are presented of the coupled neutron-gamma transport calculation of the KrŠko 632 MWe pressure water reactor (PWR). The DOT 4.2 transport code was used. The variation of gamma flux with fuel burnup was considered, and gamma flux was found to be nearly 50% higher at end of life (EOL) than at beginning of life (BOL) in the regions of interest. For Np and U dosimeters in the surveillance capsules the corrections to the measured neutron exposure due to the gamma reactions were determined. The effect of gamma heating on the temperature of the surveillance capsule and pressure vessel was calculated. The importance of gamma heating in the determination of the heatup and cooldown p-T curves for the plant was evaluated.


    pressure vessel surveillance, neutron dosimetry, gamma heating, photofission

    Author Information:

    Kodeli, I
    J. Stefan Institute, Ljubljana,

    Glumac, B
    J. Stefan Institute, Ljubljana,

    Najžer, M
    J. Stefan Institute, Ljubljana,

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP10075S