Measurements of the propagation velocity of small perturbations of the neutron flux along the height of the core of a VK-50 boiling water vessel reactor are presented. The method of measurement is based on the evaluation of the delay time of a signal between the axially positioned sensitive elements of a moving double direct-charge detector. The measurements are compared with calculations for the parameters of two-phase coolant in the measurement channels. It is shown that the agreement between the measurements and the calculations is best for the velocity of an interphase surface.
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Translated from Atomnaya Énergiya, Vol. 110, No. 5, pp. 262–266, May, 2011.
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Semidotskii, I.I., Antonov, S.N., Zhitelev, V.A. et al. Assessment of the correlation method for determining the parameters of two-phase coolant in a vk-50 core. At Energy 110, 316–322 (2011). https://doi.org/10.1007/s10512-011-9428-y
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DOI: https://doi.org/10.1007/s10512-011-9428-y