STP1001

    Analysis of First Pressure Vessel Surveillance Capsule from Kršsko Nuclear Power Plant

    Published: Jan 1989


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    Abstract

    Results of the analysis of the first pressure vessel (PV) radiation embrittlement surveillance capsule from Krško nuclear power plant are presented. The capsule was removed and tested after 1.75 effective full power years of operation. Neutron flux and spectrum were calculated with DOT 3.5 and 4.2 transport codes at the locations of the specimens in the capsule and in the pressure vessel. Nickel, iron, copper, cobalt, Np-237, and U-238 neutron dosimeters were irradiated in surveillance capsules. Experimentally determined reaction rates were compared to values calculated from the neutron transport calculation,with source strength corresponding to the nominal reactor thermal power. Good agreement (within 15%) was found for threshold neutron detectors. The STAY'SL unfolding code was used to adjust the measured and calculated reaction rates and neutron fluences.

    Shifts in the RTN temperature determined from Charpy V-notch curves for irradiated material relative to that of unirradiated materials were compared with shifts predicted by NRC Regulatory Guide 1.99, Rev. 1 and Rev. 2, at the neutron exposure of 7 to 9 E18 n∙cm−2 (ϕ(E > 1 MeV)) experienced by specimens taking into account the chemical composition of PV steel.

    Keywords:

    light water reactor, pressure vessel surveillance, neutron dosimetry, RTN, DT, shifts


    Author Information:

    Kodeli, I
    J. Stefan Institute, Ljubljana,

    Remec, I
    J. Stefan Institute, Ljubljana,

    Glumac, B
    J. Stefan Institute, Ljubljana,

    Najžer, M
    J. Stefan Institute, Ljubljana,

    Loose, A
    J. Stefan Institute, Ljubljana,


    Paper ID: STP10067S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP10067S


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