STP1490: Measurement and Calculation of WWER-440 Pressure Vessel Templates Activity for Support of Vessel Dosimetry

    Zaritsky, S. M.
    Head of Department, Head of Laboratory, Head of Laboratory, Staff Scientist, Senior Staff Scientist, Senior Staff Scientist, Russian Research Center “Kurchatov Institute,”, Moscow,

    Vikhrov, V. I.
    Head of Department, Head of Laboratory, Head of Laboratory, Staff Scientist, Senior Staff Scientist, Senior Staff Scientist, Russian Research Center “Kurchatov Institute,”, Moscow,

    Erak, D. Yu.
    Head of Department, Head of Laboratory, Head of Laboratory, Staff Scientist, Senior Staff Scientist, Senior Staff Scientist, Russian Research Center “Kurchatov Institute,”, Moscow,

    Kochkin, V. N.
    Head of Department, Head of Laboratory, Head of Laboratory, Staff Scientist, Senior Staff Scientist, Senior Staff Scientist, Russian Research Center “Kurchatov Institute,”, Moscow,

    Brodkin, E. B.
    Head of Department, Head of Laboratory, Head of Laboratory, Staff Scientist, Senior Staff Scientist, Senior Staff Scientist, Russian Research Center “Kurchatov Institute,”, Moscow,

    Egorov, A. L.
    Head of Department, Head of Laboratory, Head of Laboratory, Staff Scientist, Senior Staff Scientist, Senior Staff Scientist, Russian Research Center “Kurchatov Institute,”, Moscow,

    Pages: 10    Published: Jan 2007


    Abstract

    Activity of templates (specimens), which were cut out from the inner surface of Kola-1 and Kola-2 WWER-440 reactor pressure vessels (RPVs), were measured, and the results were used to support the RPV dosimetry. Twelve weld and two base metal templates of Kola-1 RPV were cut out after 25 fuel cycles. Thirteen weld and two base metal templates of Kola-2 RPV were cut out after 24 fuel cycles. Probes were taken from four corners of each template for dosimetry measurements. Activity of 54Mn in each probe was measured and the average activity of template material was determined. Calculations were carried out in P3S8 approximation of discrete ordinates method using the DOORS 3.2 code package and BUGLE-96 nuclear data library. Calculated activities were compared with experimental ones. Neutron fluence (for neutrons with E>0.5 MeV) was calculated and calculation uncertainty evaluated based on the comparison of calculated and measured RPV templates activities and on some results of WWER-440 mock-up experiments carried out earlier on the reactor LR-0.

    Keywords:

    reactor pressure vessel, dosimetry, activity measurement, template, 54, Mn, neutron fluence, WWER-440


    Paper ID: STP45468S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP45468S


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