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