STP1550: Retrospective Dosimetry Analyses of Reactor Vessel Cladding Samples

    Greenwood, L. R.
    Battelle Pacific Northwest National Laboratory, Richland, WA

    Soderquist, C. Z.
    Battelle Pacific Northwest National Laboratory, Richland, WA

    Fero, A. H.
    Westinghouse Electric Company, PA

    Pages: 6    Published: Aug 2012


    Reactor pressure vessel cladding samples for Ringhals Units 3 and 4 in Sweden were analyzed using retrospective reactor dosimetry techniques. The objective was to provide the best estimates of the neutron fluence for comparison with neutron transport calculations. A total of 51 stainless steel samples consisting of chips weighing approximately 100 to 200 mg were removed from selected locations around the pressure vessel and were sent to Pacific Northwest National Laboratory for analysis. The samples were fully characterized and analyzed for radioactive isotopes, with special interest in the presence of Nb-93 m. The RPV cladding retrospective dosimetry results will be combined with a re-evaluation of the surveillance capsule dosimetry and with ex-vessel neutron dosimetry results to form a comprehensive 3D comparison of measurements to calculations performed with 3D deterministic transport code.


    retrospective reactor dosimetry, Nb-93 m measurements, reactor vessel fast neutron fluence

    Paper ID: STP155020120019

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP155020120019

    CrossRef ASTM International is a member of CrossRef.