STP1550

    Neutron and Gamma Field Investigations in the VVER-1000 Mock-Up Concrete Shielding on the Reactor LR-0

    Published: Aug 2012


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    Abstract

    Two sets of neutron and gamma field investigations were carried out in the dismountable model of radiation shielding of the VVER-1000 mock-up on the LR-0 reactor. First, measurements and calculations of the 3He(n,p)T reaction rate and fast neutrons and gamma flux spectra in the operational neutron monitor channel inside a concrete shielding for different shapes and locations of the channel (cylindrical channel in a concrete, channels with collimator in a concrete, cylindrical channel in a graphite). In all cases measurements and calculations of the 3He(n,p)T reaction rate were done with and without an additional moderator-polyethylene insert inside the channel. Second, measurements and calculations of the 3He(n,p)T reaction rate spatial distribution inside a concrete. The 3He(n,p)T reaction rate measurements and calculations were carried out exploring the relative thermal neutron density in the channels and its space distribution in the concrete. Fast neutrons and gamma measurements were carried out with a stilbene (45 × 45 mm) scintillation spectrometer in the energy regions 0.5–10 MeV (neutrons) and 0.2–10 MeV (gammas).

    Keywords:

    VVER-1000, shielding, mock-up, LR-0 reactor, 3, He(, n, ,, p, )T reaction rate, fast neutrons, gammas, measurements, calculations


    Author Information:

    Zaritsky, S.
    National Research Center, Kurchatov Institute, Moscow,

    Egorov, A.
    National Research Center, Kurchatov Institute, Moscow,

    Ošmera, B.
    Research Centre Rež Ltd,, Rež,

    Mařik, M.
    Research Centre Rež Ltd,, Rež,

    Rypar, V.
    Research Centre Rež Ltd,, Rež,

    Cvachovec, F.
    Univ. of Defense, Brno,

    Kolros, A.
    Czech Technical Univ., Prague,


    Paper ID: STP155020120026

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP155020120026


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