Numerical and experimental investigations of thermalhydraulic characteristics for fast reactor vessals on integral model SARH in different operation regimes


Issue of journal:


Features of the stratified flows on examples of reactors on fast neutrons, possibility of their scale
modelling are considered. Some results of experimental and numerical researches in mixing chambers
and pipelines are presented. It is underlined necessity of the account of the stratification phenomena
at a substantiation of reliability, safety, periods of operation for various nuclear power plants.

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