Two-Dimensional Thermohydraulic Module of the Integrated Code Sokrat-BN: Mathematical Model and Computational Results


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The two-dimensional thermohydraulic model used in the thermohydraulic module of the SOKRAT-BN code is described and the computational results obtained by using it are presented. The thermohydraulic model is based on the solution of two-dimensional equations using empirical correlations for determining the intensity of the turbulent transfer of mass, energy and momentum in the radial direction. The experiments performed in the 19- and 37-pin assemblies on the Siena stand in Japan and in the 37-pin assembly in the KNS stand in Germany were calculated. The average deviations of the computed values do not exceed 10%.

作者简介

E. Usov

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

M. Kuznetsova

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

N. Pribaturin

Novosibirsk Branch, Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Novosibirsk

R. Chalyi

Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

N. Ryzhov

Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

A. Kiselev

Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

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